Text

Control Room Habitability Radiological Dose Analysis
	ML20058P640
Person / Time
Site:	Zion File:ZionSolutions icon.png
Issue date:	03/11/1993
From:	Johnson W, Klazura A, Lahti G; SARGENT & LUNDY, INC.
To:	;
Shared Package
ML20058P067	List: ML20058P065; ML20058P089; ML20058P101; ML20058P615; ML20058P633; ML20058P640;
References
	ATD-0190, ATD-0190-R02, ATD-190, ATD-190-R2, NUDOCS 9310250135
	Download: ML20058P640 (85)
	v • d • e

{{#Wiki_filter:- [ L PROJECT NAME: Zion Station UNIT No.: 1&2 SARGENT @LUNDY pro;ECT No.: 8986-10 FILE NO.:4.6. 13.1 .swome tas CuENT: Commonwealth Edison Company-SYSTEM: CR E CALC. NO.: ATD 0190 DivtSioN: ATD E DES " ^" GN V R F\\ CATI N TITLE: Control Room Habitability Radiological Dose Analysis E E PAGE 1 of X SAFETY RELATED NON SAFETY RELATED Q /- i Pages 1 - 68, all new Calculations. m e e e M. u. Jw. g R. S.' AubnEr ' 10/29/92 i o .] $ f W.g. John!Ich 1,gf29/92 f ! [/4I/kM p!***,. 3 ; [ g E b G. P. Lahti 10/29/92 iE See Page 68 I c,$ Ur;de's 6e pervi7 g / pA j,'

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Kev.seci on ly pa.gs 1, S,12.,13, ma R, d a 5 ud SC ; a.ll other 'Rav. O f ap.s A re-l L S', A hner 12/s/f-t M"ch=]td-f h, 0&hf~ h bSOeb PhfC. S$- A g. $ JJ.ll', 3 UNAsfu i>AMf2-$ I l REVIEW METHOD STATUS 15 8e.e fa.ge 67 Yttrf w/&{ [ w ? d./ lAWTi /Otr. (912-S La.-e r $ b /t~,j [ Revised All Pages (i.e., pages 1 through 85) [ 2 AnthoiF.G. K1azura 5 This revision supercedes revisions 0 and 1. 4 E f k-} - lll I s 77 - n 5 E W. J. Johnson W//A/3 8 ~l g ) l REVIEW METHOD STATUS 0 See Page 85 Verified B g ev-- v G. P. Lahti Abe447 I U er J L a N P g i s E l j h REVIEW METHOD STATUS o g E 5 1 9310250135 930901 C PDR ADDCK 05000295 l P PDR h

SARGENT & LUNDY ENGINEERS Radiological Dose Analysis new. 2 Date X Safety-Related Non-Safety Related Pace 2 of client Commonwealth Edison Company Prepared by Date Protect Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system No. CR Approved by Date TABLE OF CONTENTS Paae DESIGN CONTROL

SUMMARY

SHEET 1 TABLE OF CONTENTS 2 LIST OF TABLES 4 3. PURPOSE 5 2. DESIGN INPUT ~ 5 2.1 Source Term 5 i 2.2 Plant Data 6 i 3. ASSUMPTIONS 11 4. APPROACH 13 i 5. CALCULATIONS 14 5.1 Hand Calculations 14 5.1.4 Particulate Spray Removal Rate for Recirculated Spray 14 5.1.2 POSTDBA Effective Wind Speeds for Measured (X/Q')'s 14 5.1.3 ECCS Leakage 16 5.1.3.1 ECCS Leak Rate (POSTDBA Purge Rate) 16 5.1.3.2 POSTDBA Effective Purge Filter Efficier.cy for ECCS Leakage 17 5.1.4 Leakage Back to RWST 18 5.1.4.1 Leak Rate Back to RWST (POSTDBA Purge Rate) 18 5.1.4.2 POSTDBA Effective Purge Filter Efficiency for Leakage Back 19 to the RWST ATD-0190.VP0

cales. For Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY rsomrns Radiological Dose Analysis - Rev. 2 cate X Safety-Related Non-Safety Related Pane 3 of client Commonwealth Edison Company Precared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date IJJ1E OF CONTENTS. Cont'd EASA 5.1.5 Containment Two Compartment Volumes 19 5.1.6 Source Terms 20 5.1.6.1 Containment Leakage Source Term 20 5.1.6.2 ECCS Leakage and Leakage Back to the RWST Source Term 20 5.1.7 Containment Mixing Rate 21 5.1.8 Containment Leak Rate 21 5.2 Computer Calculations 22 5.2.1 POSTDBA Input Description 22 5.2.1.1 Input for the Containment Leakage Case ~ 5.2.1.2 Input for the ECCS Leakage Case 22 31 5.2.1.3 Input for the Leakage Back to the RWST Case 39 5.2.2 POSTDBA Run 47 5.2.3 POSTDBA Results for 144 cfm Unfiltered Inleakage to the Control Room 48 5.2.3.1 CASE 1,1600 CFM Control Room Makeup Flow Rate 48 5.2.3.2 CASE 2,1800 CFM Control Room Makeup Flow Rate 51 5.2.3.3 CASE 3, 2000 CFM Control Room Makeup Flow Rate 54 5.2.3.4 CASE 4, 2200 CFM Control Room Makeup Flow Rate 57 5.3 Total 720 Hour Doses From All Leakage Paths for 144 cfm Inleakage 60 5.4 Thyroid Doses for Other Unfiltered Inleakages 64 6. RESULTS 67 7. REFERENCES 71 ATTACHMENTS 74 REVIEW METHOD SHEET 85 ATD-0190.VP0

cales. For Control Room Habitability Calc. No. ATD-0190 SARGENT & LUNDY cuamtems Radiological Dose Analysis Rev. 2 oase X Safety-Related Non-Safety Related Pace 4 of cite,t Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by cate Prof. No. 9140-41 System No. CR Approved by cate LIST OF ATTACHMENTS USA 1. Microfiche of POSTDBA Input and OUTPUT 74 2. Reference 9 75 3. Reference 10 78 4. Reference 3 81 5. Reference 4 83 6. Reference 22 84 LIST OF TABLES DCk

1. Core Inventory of Iodine ard Noble Gas 5

2. Primary Containment Data 6

3. Containment Spray Data 8

4. Control Room Data 9

5. Effective Wind Speeds for POSTDBA Input 15

6. Airborne Iodine and Noble Gas Activities at Time Zer:

20

7. Iodine Activities in the Sump Water at Time Zero 21

8. 30 Day Control Room Doses for 144 cfm Unfiltered Inleakage 60

9. 30 Day Thyroid Doses for Table 4 Unfiltered Inleakages 65

10. 30 Day Control Room Doses and Comparison With Regulatory Limits 68 ATD-0190.VP0

SARGFNT & LUNDY cales. r r Control Room Habitability calc. No. ATD-0190 ENGWEERS Radiological Dose Analysis new. 2 cate X Safety-Related Non-Safety Related Page 5 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by oate Prof. No. 9140-41 System No. CR Approved by oate 1. PURPOSE The purpose of this calculation is to determine the 30 day control room doses following a Design Basis LOCA using measured control room inleakage rates and the maximum measured 0-8 hour (X/Q') (atmospheric dispersion). Control room doses are determined for four different makeup air flow rates. Doses based on the minimum unfiltered inleakage rates for both HVAC Train A and Train B are determined. Maximum allowable unfiltered inleakage rates are then calculated. The results are used to demonstrate compliance with 10CFR50, Appendix A, Criterion 19 - Control Room. i This revision superceeds all previous revisions to this calculation. The basis for this revision to the calculation is documented in Reference 4. 2. DESIGN INPUT 2.1 Source Term The initial airborne iodine and noble gas activities in the containment are 25% and 100% of their core inventories respectively which are released instantaneously (Ref. 1). 50% of the core inventory of iodine is in the sump water (Ref. 8, Appendix B, p. 15.6.5-16). Table 1 summarizes the end of life core inventory for operation at 3391 Mwt (about 104% of full power). Table 1 Core Inventory of Iodine and Noble Gas (Reference 2, Table 15.6-32)

Activity, Activity,

Activity, Nuclide Curies Nuclide Curies Nuclide Curies I-131 9.34E+7 Kr-85m 2.70E+7 Xe-133m 4.94E+6 I-132 1.38E+8 Kr-85 9.40E+5 Xe-133 1.88E+8

{ I-133 1.76E+8 Kr-87 5.08E+7 Xe-135m 5.20E+7 I-134 2.19E+8 Kr-88 7.70E+7 Xe-135 5.42E+7 I-135 1.78E+8 ATD-0190.VP0

l i Y SARGENT & LUNDY ENGINEERS Radiological Dose Analysis - Rev. 2 Date X Safety-Related Non-Safety Related Pace 6 of client Commonwealth Edison Company Prepared by Date project Zion Station - Units 1 & 2 Reviewed by Date Pro). No. 9140-41 system No. CR Approved by Date 2.2 Plant Data Table 2 presents primary containment data. l Table 2 Primary Containment Data h r;n Value Reference Free Volume (ft**3) 2.715E+6 Ref. 2, Subsection 15.6.5.4.4.3, p. 15.6-34 Fraction of Volume Sprayed 0.8613 Refr 15-Number of Fan Coolers During LOCA 3 ~ Tef. 5 & Ref. 2, Subsection 15.6.5.4.4.1 Fan Cooler Flow Rate (cfm per fan) 66000. Ref. 5 & Ref. 2, Table 6.2-1 Projected Area Normal to Wind (ft**2) 26436. Ref. 6, p. 18 Projected Area Normal to Wind (m**2) 2456. Ref. 6, p. 18 Leak Rate (%/ day) for 0 to 24 Hours 0.1 Ref. 7 and Ref. 2, Subsection 15.6.5.5.6.2, p. 15.6-54 Leak Rate (%/ day) for 24 to 720 Hours 0.05 Ref. 1 Elemental Iodine Fraction .91 Ref. 1 Particulate lodine Fraction .05 Ref. 1 Organic Iodine Fraction .04 Ref. I Sump Water Volume Breakdown: Minimum RWST (gal) 350000. Ref. 2, Table 6.3-4 One Accumulator (ft**3) 818. Ref. 2, Table 6.3-3 Reactor Coolant (ft**3) 12760. Ref. 2, Table 158.4-1, .p. 158-12 Spray Additive Tank (gal) 5000. Ref. 2, Table 6.5-3 Number of Accumulators 4 Ref. 2, Table 6.3-3 i

Previously, a boron injection tank water volume was included when determing the sump

) water volume. However, per Reference 22, the boron injection tank water is no longer i considered to be part of the sump water volume. ATD-0190.VP0

I

SARGENT & LUNDY i ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Pace 7 of I client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by cate Proj. No. 9140-41 system No. CR Approved by cate Table 2 (Cont'd) Item Value Reference ELCS Leak Rate (cc/hr) 1770. Ref. 2, Table 6.3-9 ECCS Leak Rate (cc/hr) To Use (2 Times) 3540. Ref. 8, p. 15.6.5-17 ESF Atmospheric Filtration Provided Ref. 2, Subsection 9.4.3.2, for ECCS Leakage

p. 9.4-7 Potential ECCS Leakage From Gross Ref. 8, p. 15.6.5-17 Failure Not Considered Sump Water Temperature (deg F) (<212) 200.

Ref. 2, Subsection 15.6.5.5.6.3, p. 15.6-55 Fraction of Iodine in ECCS Leakage That 0.1 Ref. 8, p. 15.6.5-17 Becomes Airborne ESF Exhaust Filter Fractional Efficiency for Iodines 0.90 Ref. 3 i Leak Rate Back to RWST (cc/hr) 30. Ref. 9 ATD-0190.VP0 a

cales. For Control Room Habitability caic. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis nev. 2 Date X Safety-Related Non-Safety Related Page 8 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system no. CR Approved by Date Table 3 Containment Spray Data Item Value Reference Spray Injection Delay Time (sec) 110. Ref. 9 Two Pump Spray Injection Time (minutes) 15. Ref. 10 One Pump Spray Injection Time (minutes) 38. Ref. 10 Recirculation Spray Delay Time (minutes) 30. Ref. 10 Recirculation Spray Flow Rate (gpm) 2460. Ref. 11 Spray'. Drop Fall Height (ft) 147. Ref. 2, Appendix 6B, Table 68.1 Spray Time, All Modes Including Delays 4.0 Ref. 9 ~ (days) Spray Removal Rates (1/hr) for iodines: Elemental (One or Two Injection Pumps 20.0 Ref. 12, p. 17

and DF < 200)

Particulate (Two Injection Pumps 10.3 Ref. 12, p. 28

and DF < 50)

Particulate (One. Injection Pump 5.15 Ref. 12, p. 28 * ~ and DF < 50) Organic (Two Injection Pumps) .0687 Ref. 12, Microfiche A

Organic (One Injection Pump)

.03663 Ref.12, Microfiche A

Organic (Recirculation Pump) 0.03246 Ref. 21, p. 83 Elemental Iodine Plateout Rate (1/hr) 2.41 Ref. 12, p. 19
Elemental Iodine Decontamination Factor 200.

Ref. 12, P. 18

Particulate Iodine Spray Rate Reduction 0.1 Ref. 13, p. 6.5.2-12 Factor at DF of 50 See Engineering Judgement Number 2 in Section 3.

See Engineering Judgement Number 1 in Section 3. ATD-0190.VP0

cales. r r Control Room Habitability taic. No. ATD-0190 SARGENT & LUNDY momrns Radiological Dose Analysis Rev. 2 cate X safety-Related Non-$afety Related Page 9 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 System No. CR Approved by Date Table 4 Control Room Data i Item Value Reference Free Volume (ft**3) 1.19122E+5 Ref. 14 i Make-up Air Flow Rate (cfm) 1600. Ref. 4 1800. Ref. 4 2000. Ref. 4 2 ^ 2200. Re f. ' ~ Recirculation Air Flow Rate (cfm) 11500. Ref. 14 (Value Has No Effect on Doses Because Recirculation Filter Efficiency Is Assumed Zero) Make-up Air Filter Fractional .99 Ref. 2, Efficiency for Iodines Subsection 6.4.4.1,

p. 6.4-3 Unfiltered Inleakage Rates (cfm):

Minimum From Train B 81. Ref. 9 Minimum From Train A 96. Ref. 9 Maximum From Train B 119. Ref. 9 Maximum From Train A 144. Ref. 9 (X/Q') (sec/m**3) for 0-8 Hours 6.87E-4 Ref. 16 (X/Q') (sec/m**3) for Other Times Based on 0-8 Hour Value and Ref. 17 Methodology Personnel Breathing Rate (m**3/sec) 3.47E-4 Ref. 17 Occupancy Factors: 0-24 Hours 1.0 Ref. 17 24-96 Hours 0.6 Ref. 17 96-720 Hours 0.4 Ref. 17 Thyroid Dose Conversion Factors Ref. 18 ATD-0190.VP0

cales. F r Control Room Habitability Calc. No. ATD-0190 SARGENT & LUNDY ENGNts Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Paoe 10 of ciient Commonwealth Edison Comoany Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by cate Prof. No. 9140-41 system ho. CR Approved by oat. Table 4 (Cont'd) Item Y31ue Reference Finite Cloud Correction Factors: 1-131 16.65 Ref. 12, p. 38, Table 3 I-132 18.10 Ref.12, p. 38, Table 3 1-133 17.46 Ref.12, p. 38, Table 3 I-134 18.55 Ref.12, p. 38, Table 3 I-135 20.04 Ref.12, p. 38, Table 3 Kr-85m 15.08 Ref.12, p. 38, Table 3 Kr-85 17.09 Ref.12, ~ Microfiche B-Kr-87 20.85 Ref.12, p. 38, Table 3 Kr-88 21.86 Ref.12, p. 38, Table 3 Xe-133m 6.701 Ref.12, p. 38, Table 3 Xe-133 7.976 Ref.12, p. 38, Table 3 Xe-135m 16.55 Ref.12, p. 38, Table 3 Xe-135 16.49 Ref. 12, p. 38, Table 3 4 e i ATD-0190.WP0

'"~ SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safet y-Related Non-Safety Related Page II of i citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units I & 2 Reviewed by Date Prob No. 9140-41 System No. CR Approved by Date 3. ASSUMPTIONS The following assumptions are noted. 1. ihe fraction of the initial source released to the un. sprayed containment volume !s 1.0. This is conservative because spray removal does not occur until radiciodine is transported from the unsprayed to the sprayed volume. 2. Elemental iodine plateout in the containment is conservatively ended when the elemental iodine decontamination factor is reached; thus, the plateout ends when.the spray removal ends for elemental iodine. 3. The start times for the ECCS leakage and the leakage back to the RWST are both assumed to be 15 minutes. This is a conservative assumption since the injection spray lasts at least 15 minutes; thus, the recirculation spray cannot start before 15 minutes after the LOCA. 4. The control room recirculation filter fractional efficiency for iodines is ^ conservatively assumed to be zero. 5. For ECCS leakage and leakage back to the RWST, the source term for one type i of leakage is conservatively assumed to be independent of the other type of i leakage; thus, one leakage type does not remove source activities for the other type. j i l ATD-0190.VPD j

4 1 SARGENT & LUNDY ENGMEDt3 Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Pace 12 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date The following three Engineering Judgements are made. l l 1. Elemental iodine plateout occurs in both sprayed and unsprayed volumes of the containment when the spray is operating, subject to Assumption 2. This ~' is justified by the consideration that, when the spray is on, the surfaces in both volumes are refreshed by " clean" water. The surfaces of the unsprayed volume receive this water as it falls to the sump. i 2. Reference 12 uses a containment volume and a sump water volume that are slightly different than the volumes given in Table 2 of this calculation. The differences which are of the order of one percent, if corrected,~would -{ not lead to significantly different spray removal rates and decontamination factors. Not only are the differences small, they are in certain applications conservative. This justifies the use of Reference 12 results in this calculatior.. 3. Control room whole body gamma and beta skin dose results will be calculated for the largest measured unfiltered inleakage rate arrived at via testing. Whole body gamma and beta skin doses, for unfiltered inleakage rates which are smaller than the largest measured rate, will be smaller than the calculated doses because radiological doses hre the largest for the maximum unfiltered inleakage rate. This is justified because the larger the total intake rate the sooner the equilibrium concentration will be reached; this will result in a larger dose. ATD-0190.VP0

i ' " ^ SARGENT & LUNDY tuomms Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 13 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 System No. CR Approved by Date 4. APPROACH NRC guidance found in References 1, 8, 13, 17, and 19 is used. Control room radiological doses are obtained from computer runs using Program POSTDBA, Sargent and Lundy Program Number 03.7.287-1.0 (Reference 20). The analysis addresses four control room makeup air flow rates (1600,1800, 2000, and 2200 cfm). Separate computer runs are made for containment leakage, for ECCS leakage, and for leakage back to the RWST for each of the specified control room makeup air flow rates. These computer runs use the largest (most conservative) control room unfiltered inleakage rate. ' Doses for the other. specified unfiltered inleakage rates (Table 4) are obtained using the Iodine Protection Factor (IPF) methodology described in Reference 17; the equation is (IPF) - [g+f]/[(1-n)g+f] where (IPF) - Iodine Protection Factor g - control room make-up flow rate f - control room unfiltered inleakage flow rate - control room make-up filter fractional efficiency for iodines. n ) For this calculation, g - 1600. cfm, 1800 cfm, 2000, cfm, 2200. cfm (Table 4) and n =.99 (Table 4). 4

Then, (IPF)

- (1600+f)/(16+f). EQN. la (IPF) = (1800+f)/(18+f) EQN. Ib (IPF) = (2000+f)/(20+f) EQN. Ic (IPF) = (2200+f)/(22+f) EQN. Id Also, the thyroid inhalation dose is inversely proportional to the (IPF).

Thus, i

if the thyroid dose is known for one f (e.g., f-144 cfm, Table 4), then the thyroid doses for all other values of f can be found. ATD-0190.WP0

Y SARGENT & LUNDY ENGWEERs Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page' 14 of citent Commonwealth Edison Company Prepared by cate Project Zion Station - Units 1 & 2 Reviewed by oat. Proj. No. 9140-41 System No. CR Approved by oate 5. CALCULATIONS 5.1 Hand Calculations 5.1.1 Particulate Spray Removal Rate for Recirculated Spray The particulate iodine spray removal rate, L, is given by L - [3hF/(2V)][E/D] (Ref.13, p. 6.5.2-11) where h - spray drop fall height i F = spray flow rate V - containment free volume and [E/D] - 10. (1/m) until a decontamination factor of 50 is reached (Reference 13, p. 6.5.2-12).

But, h - 147 (ft) - 44.8 (m)

(Table 3) F - 2460. (gpm) (Table 3) and V - 2.715E+6 (ft**3) (Table 2).

Then, L - [3 *44.8 (m) *2460 (gpm) *10 (1/m) *.13365 (ft**3/ gal)

60 (min /hr)]/[2 *2.715E+6 (ft**3)]

L - 4.883 (1/hr) for recirculated spray before a DF of 50 is reached. POSTDBA will automatically reduce this value by a factor 0.1 if a DF of 50 has been reached. 5.1.2 POSTDBA Effective Wind Speeds for Measured (X/Q')'s If for a given Reference 17 time period a value of (X/Q') exists, then the effective wind speed, u, that POSTDBA requires as input is defined by the relation: (X/Q') - 2/(uA) (Reference 20, Eqn. 33, p. 2-18) where A is the containment projected area normal to the wind ATD-0190.VP0

cales. r r Control Room Habitability calc. No. ATD-0190 SARGENT & LUNDY ENGINEN Radiological Dose Analysis new. 2 Date X Safety-Related Non-Safety Related Pace 15 of cuent Commonwealth Edison Company Prepared by Date Pro 3ect Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date direction. Solving for u: u = 2/[A(X/Q')]. But in this calculation, A-2456 (m**2) (Table 2). Then, if (X/Q') has units of (sec/m**3), u in units of (m/sec) is given by u - 8.1433E-4/(X/Q'). EQN. 2 In addition,1f the 0-8 hour (X/Q') is known (measured), the (X/Q') for any other time period can be found by applying the (X/Q') reduction factors (excluding occupancy) given in Reference 17. With all of this in mind, the following table (Table 5) presents the calculation of effective wind speeds for input to POSTDBA. Table 5 Effective Wind Speeds for POSTDBA Input Col. A, Col. A times EQN. 2, Ref. 17 (X/Q') Measured Calculated Reduction Re f. 16, (X/Q') - Effective Time Factor Measured Calculated Wind Speed,

Period, (Excluding (X/Q'),

(X/Q'), u, Hours Occupancy) (sec/m**3) isec/m**3) (m/sec) 0-8 1.0 6.87E-4 6.87E-4 1.185 8-24 .59 4.053E-4 2.009 24-96 .375 2.576E-4 3.161 96-720 .165 1.134E-4 7.181 ATD-0190.VP0

tales. r r Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGINEM Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 16 of citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by 04te Proj. No. 9140-41 System No. CR Approved by oate 5.1.3 ECCS Leakage 5.1.3.1 ECCS Leak Rate (POSTDBA Purge Rate) From Table 2, the ECCS leak rate is 3540 (cc/hr). Then in units of (gal /hr), ECCS leak rate (gal /hr) - 3540 (cc/hr)* 1.0E-6 (m**3/cm**3)

264.2 (gal /m**3)

ECCS leak rate .9353 (gal /hr). The volume of the leaking sump water.in which iodine activity resides is the sum of the volume breakdown given in Table 2; thus, Sump water volume (gal) - 350000 (gal) + 4*818 (ft**3)/.1337 (ft**3/ gal) + 12760 (ft**3)/.1337 (ft**3/ gal) + 5000 (gal) Sump water volume - 474910 (gal). Then, the ECCS leak rate (sump water fraction per minut:) is ECCS leak rate (1/hr) .9353 (gal /hr)/474910 (gal)/60 (min /hr) ECCS leak rate - 3.282E-8 (1/ min). In POSTDBA, this ECCS leakage can be modelled by a containment purge in which the purge rate, P, is given by d P - 3.282E-8 (1/ min)

V (ft**3) where V is the containment free volume containing the iodine activity.

The containment free volume is 2.715E+6 (ft**3) as given in Table 2. Therefore, P .08911 (cfm). l ATD-0190 APO

cales. r r Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGINEm Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 17 of client Commonwealth Edison Company Prepared by Date pro 3ect Zion Station - Units 1 & 2 Reviewed by Date Pro.l. No. 9140-41 System No. CR Approved by Dats The two pump spray injection phase lasts for 15 minutes (Table 3). Thus, the ECCS leak rate is zero for the first 15 minutes (P - 0.0). It will be conservatively assumed (Assumption Number 3) that the recirculation phase starts at 15 minutes (P .08911 (cfm)) and lasts for 30 days. Note that to use this modelling, the POSTDBA containment leak rate must be set to zero. 5.1.3.2 POSTDBA Effective Purge Filter Efficiency for ECCS Leakage From Table 2,10 percent of the iodine in the ECCS leakage becomes airborne because the sump water temperature is less than 212 deg F. This is the conservative maximum amount. The airborne iodine is instantaneously exhausted (conservative) to the atmosphere through a 1 90 percent efficient filter (Table 2). Thesa iodine reduction capabilities can be represented in POSTDBA by setting the POSTDBA purge filter fractional efficiency, E, so that (1-E) - (1-E')F where E' is the actual filter fractional efficiency .90 and F is the fraction of iodine in the sump water that is airborne .10.

Then, E F+FE' E - 1.10+.10*.90 E

.99. I ATD-0190.VP0

I * ' SARGENT & LUNDY Examstas Radiological Dose Analysis Rev. 2 cate X Saf ety-Related Non-Safety Related Page 18 of client Commonwealth Edison Company Prepared by Date Pro 1ect Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system no. CR Approved by Date 5.1.4 Leakage Back to RWST 5.1.4.1 Leak Rate Back to RWST (POSTDBA Purge Rate) From Table 2, the leak rate back to the RWST is 30 (cc/hr). Then in units of (gal /hr), Leak rate (gal /hr) back to RWST - 30 (cc/hr)* 1.0E-6 (m**3/cm**3)

264.2 (gal /m**3)

Leak rate back to RWST .00793 (gal /hr). The volume of the leaking sump water in which iodine activity resides is given in-Subsection 5.1.3.1: ' ~ ' Sump water volume - 474910 (gal). Then, the leak rate back to the RWST (sump water fraction per minute) is Leak rate back to RWST (1/hr) =.00793 (gal /hr)/474910 (gal)/60 (min /hr) Leak rate back to RWST - 2.783E-10 (1/ min). In POSTDBA, this ECCS leakage can be modelled by a containment purge in which the purge rate, P, is given by P - 2.783E-10 (1/ min)

V (ft**3) where V is the containment free volume cc.taining the iodine activity.

The containment free volume is 2.715E+6 (ft**3) as given in Table 2. Therefore, P - 7.556E-4 (cfm). The two pump spray injection phase lasts for 15 minutes-(Table 3). Thus, the leak rate back to the RWST is zero for the first 15 minutes (P - 0.0). It will be conservatively assumed (Assumption Number 3) that the recirculation phase starts at 15 minutes (P - 7.556E-4 (cfm)) ATD-0190 NP0

cales. r r Control-Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGWEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Pace 19 of citent Commonwealth Edison Company Prepared by Date J Project Zion Station - Units 1 & 2 Revie ed by Date Prof. No. 9140-41 System No. CR Approved by Date and lasts for 30 days. Note that to use this modelling, the POSTDBA containment leak rate must be set to zero. 5.1.4.2 POSTDBA Effective Purge Filter Efficiency for Leakage Back to the RWST From Table 2,10 percent of the iodine in the ECCS leakage becomes airborne because the sump water temperature is.less than 212 deg F. This is the conservative maximum amount. The airborne iodine is l instantaneously exhausted, unfiltered (conservative), to the atmosphere. This iodine reduction capability can be represented in POSTDBA by setting the POSTDBA purge filter fractional efficiency, E, so that (1-E) - F where F is the fraction of iodine in the sump water that is airborne .10.

Then, E = l-F E - 1.10 E

.90. 5.1.5 Containment Two Compartment Volumes The containment is divided into two compartments - an " upper" volume which can be sprayed and a " lower" volume which is not sprayed. In I POSTDBA, the " lower" volume is termed " volume 1", and the " upper volume" is termed " volume 2". From Table 2, the containment total free volume is 2.715E+6 (ft**3), and the fraction of this volume that is sprayed is 0.8613. Then, for POSTDBA input, Volume 1 = {l.0-0.8613)*2.715E+6 - 3.7657E+5 (ft**3), and Volume 2 - 0.8613*2.715E+6 - 2.33843E+6 (ft**3). ATD-0190.WP0

~ SARGENT & LUNDY mamms Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 20 of citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system No. CR Approved by Date 5.1.6 Source Terms 5.1.6.1 Containment Leakage Source Term Table 1 provided the core inventory of iodines and noble gases. Section 2.1 gave the fractions airborne in the containment at zero time. The following table (Table 6) gives the. airborne iodine and noble gas activities at zero time (fraction airborne times core inventory). Table 6 Airborne Iodine and Noble Gas Activities at Time Zero (Section 2.1 and Table 1)

Activity, Activity,

Activity, Nuclide Curies Nuclide

- Curies Nuclide Curies I-131 2.335E+7 Kr-85m 2.70E+7 Xe-133m 4.94E+6 I-132 3.450E+7 Kr-85 9.40E+5 Xe-133 1.88E+8 I-133 4.400E+7 Kr-87 5.08E+7 Xe-135m 5.20E+7 I-134 5.475E+7 Kr-88 7.70E+7 Xe-135 5.42E+7 I-135 4.450E+7 5.1.6.2 ECCS Leakage and Leakage Back to the RWST Source Term Table 1 provided the core inventory of iodines. Section 2.1 gave the fractions of those activities in the sump water. These are the activities available for both ECCS leakage and leakage back to the RWST. The following table (Table 7) gives the activities in the sump water (fraction in the sump water times core inventory). ATD-0190. 'n'P0

alcs. For Control Room Habitability Calc. No. ATD-0190 SARGENT & LUNDY ENGINEDtS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 21 of I citent Commonwealth Edison Company Prepared by Date Protect Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system no. CR Approved by Date Table 7 Iodine Activities in the Sump Water at Time Zero (Section 2.1 and Table 1)

Activity, Nuclide Curies I-131 4.670E+7 I-132 6.900E+7 I-133 8.800E+7 I-134 1.095E+8 I-135 8.900E+7 For each type of leakage, the source term is conservatisely assumed to be independent of the other type of leakage; thus, one leakage type does not remove source activities for the other type (Assumption 5).

5.1.7 Containment Mixing Rate From Table 2, the number of fan coolers operating during a LOCA is 3, and the fan cooler flow rate is 66000 cfm per fan. Therefore, Containment Mixing Rate - 3* 66000 (cfm); Containment Mixing Rate - 198000 (cfm). 5.1.8 Containment Leak Rate Table 2 gives a containment leak rate of 0.1 %/ day for 0 through 24 hours after the LOCA, and a leak rate of 0.05 %/ day for 24 through 720 hours after the LOCA. In units of 1/hr these leak rates become: Leak Rate (0-24 hrs) = 0.1 (%/ day) *.01 (1/%)/ 24 (hr/ day) - 4.167E-5 (1/hr) and Leak Rate (24-720 hrs) - 0.05 (%/ day) *.01 (1/%)/ 24 (hr/ day) - 2.083E-5 (1/hr) I l ATD-0190.VP0

'*I 'I~"' SARGENT & LUNDY ~ ENGD4EERS Radiological Dose Analysis new. 2 cate X Safety-Related Non-Safety Related Pace 22 of 1 client Commonwealth Edison Company Prepared by oate Project Zion Station - Units 1 & 2 neviewed by cate Pro 3. 80. 9140-41 System No. CR Approved by Date 5.2 Computer Calculations 5.2.1 POSTDBA Input Description This calculation determines control room doses for four control room makeup filter air flow rates (1600 cfm,1800 cfm, 2000 cfm, and 2200 cfm). The analysis associated with each makeup air flow rate value is considered to be a case. Thus, there are four cases representing the four makeup air flow rate values, considered. There are three POSTDBA files per case - one for each type of activjty release. These POSTDBA files are for: 1. Containment Leakage (input description in Subsection 5.2.1.1) 2. ECCS Leakage (input description in Subsection 5.2.1.2) 3. Leakage Back to the RWST (input description in Subsection 5.2.1.3). All three POSTDBA files will be strung together to comprise one computer run per case. Input instructions are found in Reference 20, pp. 4-1 through 4-23. The input for one computer run starts with three lines naming the output file or printer and giving printer control parameters. For this run the output will appear on file POSTDBA.00T in the current directory; thus, the first line contains: POSTDBA.0UT. Since a printer is not used, the next two lines are left blank. 5.2.1.1 Input for the Containment Leakage Case Line types 4 and 5 contain the case title, JITLE: ZION 1 & 2, PROJ. N0. 9140-41, CONTROL RM DOSES FROM CONT. LEAKAGE WITH 144 CFM INLEAKAGE TO CONTROL RM CASE 1, 1600 CFM MAKEUP FLOW 9 ATD-0190,WP0

'I " ' ~ SARGENT & LUNDY m omEEns Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 23 of client Commonwealth Edison Company Prepared by cate Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system No. CR Approved by Date Title information (i.e., line types 4 and 5) are also given for Case 2, 3, and 4 computer runs (i.e., for control room makeup flow rates of 1800, 2000, and 2200 cfm, respectively). Line type 6 contains the following control parameters: ITIME - 10 No. of time intervals 10CC 2 Apply occupancy factors after dose calculation ICI 0 Don't calculate containment finite cloud corrections IC2 0 Don't calculate control room finite cloud corrections HET 0 Don't read meteorological data INL 0 Effective wind speeds will be read in IPAG1 - 0 Don't output nuclide page type 1 IPAG2-- 1 Output nuclide page type 2 including control room doses IPAG3 - 0 Don't output nuclide page type 3 JPAGI - 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 i Line type 7 contains the following data: TDECAY 0.0 Radioactivity decay time before accident V1 3.7657E+5 Unsprayed containment volume (ft**3), Subsection 5.1.5 V2 2.33843E+6 Sprayed containment volume (ft**3), Subsection 5.1.5 AREA 26436. Containment projected area (ft**2), Table 2 FI(1) = .91 Initial iodine elemental species fraction, Table 2 FI(2) - .05 Initial iodine particulate species fraction, { Table 2 FI(3) - .04 Initial iodine organic species fraction, Table 2 ATD-0190.WP0 l

3 ARGENT & LUNDY cales. r r Control Room Habitability calc. No. ATD-0190 ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 24 of i l cuent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Pro 1. No. 9140-41 system No. CR Approved by cate Line type 8 contains the following data: DCON(1) = 200.0 Elemental iodine spray decontamination factor, Table 3 DCON(2) = 0.0 Particulate iodine DF will not affect spray removal DCON(3) = 0.0 Organic iodine DF will not affect spray removal PRED 0.1 Particulate iodine spray removal rate reduction factor at DF - 50, Table 3 DCONP 50.0 Particulate iodine spray decontamination factor at which the spray removal rate reduction factor will be applied, Table 3 FCONT 1.0 Fraction of initial source that is released to the unsprayed containment volume, Assumption 1 Line type 9 contains the following data: PPFILT(1) - 0.0 Not used PPFILT(2) = 0.0 Not used PPFILT(3) - 0.0 Not used PFILT(1) 0.0 Not used PFILT(2) 0.0 Not used = PFILT(3) 0.0 Not used VC 1.19122E+5 Control room volume (ft**3), Table 4 l ATD-0190.VP0

cales. F r Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY s omEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 25 of client Commonwealth Edison Company prepared by cate Project Zion Station - Units 1 & 2 Reviewed by oate Proj. No. 9140-41 syst m No. CR Approved by oate i Line type 10 contains the following data (10 lines total *): From Table 3 Subsect. 5.1.8 Elemental Part. Organic Iodine Iodine Iodine Cont. Spray Spray Spray Purge Ending Leak Removal Removal Removal Rate

Time, Rate,

Rate, Rate,

Rate, Not Not Hours 1/hr 1/hr 1/hr 1/hr Used Used

.03056 4.167E-5 0.0 0.0 0.0, 0.0 0.0 .28056 4.167E-5 20.00 10.3 .0687 0.0 0.0 .91389 X X 5.15 .03663 X X 1.41389 X X 0.0 0.0 X X 2.0 X X 4.883 .03246 X X 4.0 X X X X X X 8.0 X X X X X X 24.0 X X X X X X 96.0 2.083E-5 X X X X X i 720.0 X X 0.0 0.0 X X i

In tables of this type on this and following pages, each line contains data for a time period defined by the "Ending Time" on the previous line (beginning time) and the "Ending Time" on the current line; however, the beginning time for the i

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. ATD-0190.VPD

54 Y 'I*' " ~ SARGENT & LUNDY ENoINEERS Radiological Dose Analysis new. 2 cate X Safety-Related Non-$afety Related Page 26 er client Commonwealth Edison Company Prepared by Date tro3ect Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system No. CR Approved by Date Line type 11 contains the following data (10 lines total): From Table 3 From Subsection El em. Elem. 5.1.7 Iodine Iodine Offsite Vol. I Vol. 2 Cont. Breathing Ending Plate Plate Mixing Rate

Time, Rate,

Rate, Not Not

Rate, Not Hours 1/hr 1/hr Used Used cfm Used

.03056 0.0 0.0 0.0 0.0 1.98E5 3.47E-4 .28056 2.41 2.41 0.0 0.0 X X .91389 X X X X X X 1.41389 X X X X X X 2.0 X X X X X X 4.0 X X X X X X 8.0 X X X X X X 24.0 X X X X X 1.75E-4 96.0 X X X X X 2.32E-4 720.0 0.0 0.0 X X X X ATD-0190,VP0

t celes. F r Control Room Habitability cale. no. ATD-0190 SARGENT & LUNDY Escrutras Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 27 or c uent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proi. ho. 9140-41 system no. CR Approved by Date t Line type 12 contains the follo' sing data (10 lines total): Table 4, Control Room I Fersonnel Ending Breathing

Time, Not Not Not Not

Rate, Hours Used Used Used Used m**3/sec

.03056 0.0 0.0 0.0 0.0 3.47E-4 ~ .28056 0.0 0.0 0.0 0.0 3.47E-4 .91389 X X X X X 1.41389 X X X X X 2.0 X X X X X 4.0 X X X X X 8.0 X X X X X 24.0 X X X X X 96.0 X X X X X 720.0 X X X X X i f 1 ATD-0190.VP0

cales. For Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY twowstas Radiological Dose Analysis new. 2 Date X safety-Related Non-Safety Related Page 28 of citent Commonwealth Edison Company Prepared by Date Proiect Zion Station - Units 1 & 2 Reviewed by cate Pro 3. No. 9140-41 System No. CR Approved by Date Line type 13 contains the following data (10 lines total): From Table 5 From Table 4 Cont. Leakage Purge Control Control Control Effective Eff. Control Room Room Room Ending Wind Wind Room Make-up Infilt. Recirc.

Time, Speed,

Speed, Occ.

Rate, Rate,

Rate, Hours m/sec m/sec Factor cfm cfm cfm

.03056 1.185 1.185 1.0 1600.0* 144.0 11500.0* .28056 X X X X X X .91389 X X X X X X 1.41389 X X X X X X 2.0 X X X X X X 4.0 X X X X X X 8.0 X X X X X X 24.0 2.009 2.009 X X X X 96.0 3.161 3.161 .6 X X X 720.0 7.181 7.181 .4 X X X 1 The value of 1600.0 cfm will be replaced by the values 1800.0 cfm, 2000.0 cfm, and 2200.0 cfm for POSTDBA input files to Case 2, ~, and 4 computer runs, respectively. Per Assumption 4, Section 3, the control room recirculation filter fractional efficiency for iodines is assumed to be 0. As such, the control room recirculation rate will have no impact on the POSTDBA results. Thus, the control room recirculation rate will be set equal to 0. cfm for POSTDBA input files for computer runs associated with cases 2, 3, and 4, i.e., makeup air flow } rates of 1800.0, 2000.0, and 2200.0 cfm, respectively. ) } ATD-0190.WP0

tales. F r Control Room Habitability calc. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 29 of c uent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proi. No. 9140-41 System Ne. CR Approved by Date Line type 14 contains the following data (10 lines total): Control Room Control Room Make-up Filter Recirculation Filter Fractional Efficiency Fractional Efficiency From Table 4 From Assumption 4 Ending

Time, Elemental Part.

Organic Elemental Part. Organic Hours Iodine Iodine Iodine Iodine Iodine Iodine .03056 .99 .99 .99 U.0 0.0 0.0 .28056 X X X X X X .91389 X X X X X X 1.41389 X X X X X X 2.0 X X X X X X 4.0 X X X X X X 8.0 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 Line types 15 through 19 are omitted. Line type 20 contains the following control parameters: IRPT = 0 Read nuclide data on line type 21 through 27 as required NUC -1 Omit reading nuclide basic parameters on line type 22 l 4 ATD-0190.VPo

cales. For Control Room Habitability tale. No. ATD-0190 SARGENT & LUNDY m amtens Radiological Dose Analysis Rev. 2 Date X Safety-pelated Non-Safety Related Page 30 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system No. CR Approved by Date Line type 21 contains the following data (13 lines total): Table 4, Control Table 6, Room Airborne Finite Nucl. Don't Activity, Cloud Not Name Print curies Factor Used I-131 0 2.335E+7 16.65 0.0 1-132 0 3.450E+7 - 18.10 0.0 ~ I-133 0 4.400E+7 17.46 0.0 1-134 0 5.475E+7 18.55 0.0 1-135 0 4.450E+7 20.04 0.0 XE-33M 0 4.940E+6 6.701 0.0 XE-133 0 1.880E+8 7.976 0.0 XE-35M 0 5.200E+7 16.55 0.0 XE-135 0 5.420E+7 16.49 0.0 KR-85M 0 2.700E+7 15.08 0.0 KR-85 0 9.400E+5 17.09 0.0 KR-87 0 5.080E+7 20.85 0.0 KR-88 0 7.700E+7 21.86 0.0 Line type 22 is omitted. Line type 23 contains the string END starting in column 1. Line types 24 through 30 are omitted. ATD-0190.WPD

b SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 31 of cuent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system no. CR Approved by Date 5.2.1.2 Input for the ECCS Leakage Case Line types 4 and 5 contain the case title, JITLE: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM ECCS LEAK FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 1, 1600 CFM MAKEUP FLOW. Title information (i.e., line types 4 and 5) are also given for Case 2, 3, and 4 computer runs (i.e., for control room makeup flow rates of 1800, 2000, and 2200 cfm, respectively). Line type 6 conti. ins the following control parameters: i ITIME - 10 Fo. of time' intervals 10CC 2 Apply occupancy factors after dose calculation ICI 0 Don't calculate containment finite cloud corrections IC2 0 Don't calculate control room finite cloud corrections MET 0 Don't read meteorological data a INL 0 Effective wind speeds will be read in IPAG1 - 0 Don't output nuclide page type 1 IPAG2 - 1 Output nuclide page type 2 including control room 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 Line type 7 contains the following data: TDECAY - 0.0 Radioactivity decay time before accident VI 3.7657E+5 Unsprayed containment volume (ft**3), Subsection 5.1.5 V2 2.33843E+6 Sprayed containment volume (ft**3), Subsection 5.1.5 AREA 26436. Containment projected area (ft**2), Table 2 FI(l) .91 Initial iodine elemental species fraction, Table 2 FI(2) .05 Initial iodine particulate species fraction, Table 2 FI(3) .04 Initial iodine organic species fraction, Table 2 = ATD-0190.VP0

ales. F r n m a a y taic. No. A D-0190 [ SARGEbM' & LUNDY ENGDJEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 32 of client Commonwealth Edison Company Prepard by Date Pro:tect Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system No. CR Approved by Date i Line type 8 contains the following data: DCON(1) = 0.0 Spray not used DCON(2) = 0.0 Spray not used DCON(3) = 0.0 Spray not used PRED - 0.0 Spray not used DCONP - 0.0 Spray not used FCONT - 1.0 Fraction of initial source that is released to the unsprayed containment volume; since spray is not used, this could be any value between 0.0 and 1.0 inclusive. Line type 9 contains the following data: PPFILT(1) - 0.0 Not used PPFILT(2) = 0.0 Not used PPFILT(3) - 0.0 Not used PFILT(1) =.99 Purge filter effective fractional efficiency for elemental iodine, Subsection 5.1.3.2 PFILT(2) .99 Purge filter effective fractional efficiency for particulate iodine, Subsection 5.1.3.2 PFILT(3) =.99 Purge filter effective fractional efficiency for organic iodine, Subsection 5.1.3.2 VC = 1.19122E+5 Control room volume (ft**3), Table 4 ATD-0190.WPD

i 'I Y 'I SARGENT & LUNDY ENGINEERS Radiological Dose Analysis new. 2 cate X Safety-Related Non-Safety Related Pace 33 or tisent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system no. CR Approved by Date i Line type 10 contains the.following data (10 lines total): Not Used Elemental Part. Organic Iodine Iodine Iodine Subsec. Cont. Spray Spray Spray 5.1.3.1, Ending Leak Removal Removal Removal Purge

Time, Rate,

Rate, Rate,

Rate, Rate, Not Hours 1/hr 1/hr 1/hr 1/hr cfm Used

.25 0.0 0.0 0.0 0.0 0.0 0.0 .50 X X X X .08911 X .88333 7 X X X X X 1.38333 X X X X X X 2.0 X X X X X X 6.0 X X X X X X 8.0 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 i ATD-0190.WP0

SARGENT & LUNDY ENOMEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Pace ?# of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date l Pro 3. No. 9140-41 System No. CR Approved by Date j l i Line type 11 contains the following data (10 lines total): Not Used From Subsection El em. Elem. 5.1.7 Iodine Iodine Offsite Vol. 1 Vol. 2 Cont. Breathing l Ending Plate Plate Mixing Rate

Time, Rate,

Rate, Not Not

Rate, Not Hours 1/hr 1/hr Used Used cfm Used l

.25 0.0 0.0 0.0 0.0 1.98E+5 3.47E-4 ~ l .50 X X X X X X .88333 X X X X X X l 1.38333 X X X X X X 2.0 X X X X X X I i 6.0 X X X X X X 8.0 X X X X X X 24.0 X X X X X 1.75E-4 96.0 X X X X X 2.32E-4 l 720.0 X X X X X X l l ATD-0190.WPD

cales. For Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGINEDtS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 35 of client Commonwealth Edison Company Prepared by Date Pro ject Zion Station - Units 1 & 2 Reviewed by oate Proj. No. 9140-41 System no. CR Approved by Date Line type 12 contains the following data (10 lines total): Table 4, control Room Personnel Ending Breathing

Time, Not Not Not Not

Rate, Hours Used Used Used Used m**3/ sac i

.25 0.0 0.0 0.0 0.0-3.47E-4 .50 X X X X X .88333 X X X X X 1.38333 X X X X X 2.0 X X X X X i 6.0 X X X X X 8.0 X X X X X 24.0 X X X X X j 96.0 X X X X X 720.0 X X X X X ATD-019 0. P D

SARGENT & LUNDY ENGNEERs Radiological Dose Analysis Rev. 2 cat. X Safety-Related Non-Safety Related Page 36 of client Commonwealth Edison Company Prepared by Date Pro ject Zion Station - Units 1 & 2 Reviewed by oate Proj. No. 9140-41 system no. CR Approved by cate Line type 13 contains the following data (10 lines total): From Table 5 From Table 4 Cont. Leakage Purge Con t.rol Control Control Effective Eff. Control Roon Room Room Ending Wind Wind Room Make-up Infilt. Recire.

Tima, Speed,

Speed, Occ.

Rate, Rate,

Rate, Hourr m/sec m/sec factor cfm cfm cfm

~ .25 1.185 1.185 1.0 1600.0* 144.0 0.0 ~ .50 X X X X X X .88333 X X X X X X 1.38333 X X X X X X 2.0 X X X X X X 6.0 X X X X X X 8.0 X X X X X X 24.0 2.009 2.009 X X X X 96.0 3.161 3.161 .6 X X X 720.0 7.181 7.181 .4 X X X The value of 1600.0 cfm will be replaced by the values 1800.0 cfm, 2000.0 cfm, and 2200.0 cfm for POSTDBA input files to Case 2, 3, and 4 computer runs, respectively. ATD-0190.VP0

cales.' r r Control Room Habitability tale. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radinlogical Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 37 of j l citent Commonwealth Edison Company Prepared by Date Pro 3ect Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 System No. CR Approved by Date i i l Line type 14 contains the following data (10 lines total): { Control Room Control Room l Make-up Filter Recirculation Filter Fractional Efficiency Fractional Efficiency From Table 4 From Assumption 4 Ending

Time, Elemental Part.

Organic Elemental Part. Organic Hours Iodine Iodine Iodine Iodine Iodine Iodine 1 .25 .99 .99 .99 0.0 0.0 - - 0.0 T~ ,4 ~ - .50 X' X X X' X X .88333 X X X X X X 1.38333 X X X X X X 2.0 X X X X X X 6.0 X X X X X X 8.0 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 Line types 15 through 19 are omitted. Line type 20 contains the following control parameters: IRPT = 0 Read nuclide data on line type 21 through 27 as required i NUC -1 Omit reading nuclide basic parameters on line type 22 l I ATD-0190.VP0 i

i i Y 'I*'"'^ ~ SARGENT & LUNDY ENGMEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 38 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proi. No. 9140-41 system No. CR Approved by Date Line type 21 contains the following data (5 lines total): Table 4, Control Table 7, Room Airborne Finite Nucl. Don't Activity, Cloud Not Name Print Curies Factor Used I-131 0 4.670E+7 16.65 0.0 I-132 '- 0 6.900E+7~ ,_l,8 10 - _ ~ 0. U'- 3 I-133 0 8.800E+7 17.46 0~.0 I-134 0 1.095E+8 18.55 0.0 1-135 0 8.900E+7 20.04 0.0 Line type 22 is omitted. Line type 23 contains the string END starting in column 1. Line types 24 through 30 are omitted. ATD-0190.VPD

Y ' " ~ ~ SARGENT & LUNDY Enomtras Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Pace 39 of client Commonwealth Edison Company Prepared by oate Project Zion Station - Units 1 & 2 Reviewed by oate Prof. No. 9140-41 System No. CR Approved by Date ) 5.2.1.3 Input for the Leakage Back to the RWST Case Line types 4 and 5 contain the case title, JITLE: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM LEAK TO RWST FOR 144 CFM j INLEAKAGE TO CONTROL RM. CASE 1, 1600 CFM MAKEUP FLOW. Title information (i.e., line types 4 and 5) are also given for Case 2, 3, and 4 { computer runs (i.e., for control room makeup flow rates of 1800, 2000, and 2200 cfm, j respectively). Line type 6 contains the following control parameters: ITIME - 10 No. of time intervals IOCC 2 Apply occupancy factors after dose calculation ICI 0 Don't calculate containment finite cloud 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 IPAGI = 0 Don't output nuclide page type 1 IPAG2 - 1 Output nuclide page type 2 including control room 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 Line type 7 contains the following data: TDECAY - 0.0 Radioactivity decay time before accident l VI - 3.7657E+5 Unsprayed containment volume (ft**3), Subsection 5.1.5 V2 - 2.33843E+6 Sprayed containment volume (ft**3), Subsection 5.1.5 AREA - 26436. Containment projected area (ft**2), Table 2 FI(l) .91 Initial iodine elemental species fraction, Table 2 FI(2) .05 Initial iodine particulate species fraction, Table 2 FI(3) .04 Initial iodine organic species fraction, Table 2 ATD-0190.WP0

w cales. For Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 40 of citent Commonwealth Edison Company Prepared i,y Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system No. CR Approved by Date Line type 8 contains the following data: DCON(1) = 0.0 Spray not used DCON(2) = 0.0 Spray not used DCON(3) = 0.0 Spray not used PRED - 0.0 Spray not used DCONP - 0.0 Spray not used FCONT = 1.0 Fraction of initial source that is released to the unsprayed containment volume; since spray is not used, this could be any value between 0.0 and 1.0 inclusive. Line type 9 contains the following data: PPFILT(1) - 0.0 Not used PPFILT(2) - 0.0 Not used PPFILT(3) = 0.0 Not used PFILT(1) .90 Purge filter effective fractional efficiency for elemental iodine, Subsection 5.1.4.2 PFILT(2) =.90 Purge filter effective fractional efficiency for particulate iodine, Subsection 5.1.4.2 PFILT(3) .90 Purge filter effective fractional efficiency for organic iodine, Subsection 5.1.4.2 VC = 1.19122E+5 Control room volume (ft**3), Table 4 I e

l Y SARGENT & LUNDY ENGINEEu Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 41 of client Commonwealth Edison Company Prepared by Date i Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system No. CR Approved by Date Line type 10 contains the following data (10 lines total): Not Used i Elemental Part. Organic lodine Iodine Iodine Subsec. Cont. Spray Spray Spray 5.1.4.1, Ending Leak Removal Removal Removal Purge

Time, Rate,

Rate, Rate,

Rate, Rate, Not Hours 1/hr 1/hr 1/hr 1/hr cfm Used

.25 0.0 0.0 0.0 0.0 0.0 0.0 .50 X X X X 7.556E-4 X .88333 X X X X X X 1.38333 X X X X X X 2.0 X X X X X X i 6.0 X X X X X X 8.0 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 i I l i i ATD-0190.VP0

) i Y ~ SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 42 or i i client Commonwealth Edison Company Prepared by Date Pro ject Zion Station - Units 1 & 2-Reviewed by Date i Proj. No. 9140-41 System No. CR Approved by Date Line type 11 contains the following data (10 lines total): Not Used From Subsection Elem. El em. 5.1.7 Iodine Iodine Offsite Vol. 1 Vol. 2 Cont. Breathing Ending Plate Plate Mixing Rate

Time, Rate,

Rate, Not Not

Rate, Not Hours 1/hr 1/hr Used used cfm Used

.25 0.0 0.0 0.0 0.0 1.98E+5 3.47E-4 .50 X X X X X X .88333 X X X X X X 1.38333 X X X X X X 2.0 X X X X X X 6.0 X X X X X X 8.0 X X X X X X 24.0 X X X X X 1.75E-4 96.0 X X X X X 2.32E-4 720.0 X X X X X X l l ATD-0190AP0

i I" ' ' ' Y C' I ~ " ~ ^ ' l SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 43 of i client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Pro j. No. 9140-41 system no. CR Approved by Date Line type 12 contains the following data (10 lines total): Table 4, Control Room Personnel Ending Breathing

Time, Not Not Not Not

Rate, Hours Used Used Used Used m**3/sec

.25 0.0 0.0 ~ 0.0 0.0-3.47E-4 .50 X X X X ~ X .88333 X X X X X 1.38333 X X X X X 2.0 X X X X X 6.0 X X X X X 8.0 X X X X X 24.0 X X X X X 96.0 X X X X X 720.0 X X X X X I ATD-0190.VP0

cales. ror Control Room Habitability cale. no. ATD-0190 SARGENT & LUNDY ENGMEDtS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 44 of titent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date Line type 13 contains the following data (10 lines total): From Table 5 From Table 4 Cont. Leakage Purge Control Control Control Effective Eff. Control Room Room Room Ending Wind Wind Room Make-up Infilt. Recirc.

Time, Speed,

Speed, Occ.

Rate, Rate,

Rate, Hours m/sec m/sec Factor cfm cfm cfm

.25 1.185 1.185 1.0 1600.0* 144.0 0.0 .50 X X X X X X .88333 X X X X X X ' 38333 X X X X X X 2.0 X X X X X X 6.0 X X X X X X 8.0 X X X X X X 24.0 2.009 2.009 X X X X 96.0 3.161 3.161 .6 X X X 720.0 7.181 7.181 .4 X X X The value of 1600.0 cfm will be replaced by the values 1800.0 cfm, 2000.0 cfm, and 2200.0 cfm for POSTDBA input files to Case 2, 3, and 4 computer runs, respectively. l l i ATD-0190.VP0

1 Y ~ SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 45 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. cps Approved by Date Line type 14 contains the following data (10 lines total): Control Room Control Room Make-up Filter Recirculation Filter Fractional Efficiency Fractional Efficiency From Table 4 From Assumption 4 Ending

Time, Elemental Part.

Organic Elemental Part. Organic Hours Iodine Iodine Iodine Iodine Iodine Iodine ~.25 .99 .99 .99 0.0 0.0 0.0 .50 X X X X X X .88333 X X X X X X 1.38333 X X X X X X 2.0 X X X X X X 6.0 X X X X X X 8.0 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 Line types 15 through 19 are omitted. Line type 20 contains the following control parameters: IRPT = 0 Read nuclide data on line type 21 through 27 as required NUC -1 Omit reading nuclide basic parameters on line type 22 ATD-0190.WP0

'I**' I '* I ' " ' ^ ~ SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 46 of citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system no. CR Approved by oate Line type 21 contains the following data (5 lines total): Table 4, Control Table 7, Room Airborne Finite Nucl. Don't Activity, Cloud Not Name Print Curies Factor Used I-131 0 4.670E+7 16.65 0.0 1-132 0 6.900E+7 18.10 0.0 I-133 0 8.800E+7 17.46 0.0 1-134 0 1.095E+8 18.55 0.0 1-135 0 8.900C+7 20.04 0.0 Line type 22 is omitted. Line type 23 contains the string END starting in column 1. Line types 24 through 30 are omitted. ATD-0190.VP0

SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date l X safety-Reinted Non-Safety Related Page 47 of client Commonwealth Edison Company Prepared by Date project Zion Station - Units 1 & 2 Reviewed by Date prof. no. 9140-41 system No. CR Approved by Date 5.2.2 POSTDBA Run POSTDBA was run using the controlled program file, POSTDBA, on the Sargent and Lundy APPLIST. The input files were POSTDBA1.INP, POSTDBA2.INP, POSTDBA3.INP, and POSTDBA4.INP.for cases 1 through 4, respectively. Similarly, the output files were POSTDBA1.00T, POSTDBA2.0VT, POSTDBA3.00T, and POSTDBA4.00T for cases 1 through 4, respectively. The input and output files for all four cases were strung together and processed.by netq to obtain microfiche. That microfiche is included as Attachment I to this calculation. ATD-0190.VPD

.. ~. a es. r n m a a y tal. N. D-0190 SARGENT & LUNDY-tuomtras Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 48 of client Commonwealth Edison Company Prepared by Date f Pro.ieet Zion Station - Units 1 & 2 Reviewed by oate f Proj. No. 9140-41 System No. CR Approved by Date j 5.2.3 POSTDBA Results for 144 cfm Unfiltered Inleakage to the Control Room 5.2.3.1 CASE 1,1600 CFM Control Room Makeup Flow Rate i 5.2.3.la Containment Leakage Results .l i The control room doses for the containment leakage source were: a ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM CONT. LEAXAGE USING 144 CFM INLEAKAGE TO CONTROL RM. CASE 1, 1600 CFM Makeup Flow SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE,' REM------------

]

TIME, BODY SKIN SKIN SKIN HOURS GAPMA GAPMA BETA TOTAL THYROID

.031 2.829E-05 4.078E-05 3.307E-04 3.715E-04 1.290E-02 .281 1.953E-03 2.804E-03 2.355E-02 2.635E-02 5.294E-01 .338 2.727E-03 3.912E-03 3.301E-02 3.692E-02 6.629E-01 .715 9.846E-03 1.411E-02 1.200E-01 1.341E-01 1.483E+00 .914 1.462E-02 2.095E-02 1.777E-01 1.987E-01 1.880E+00 1.414 2.814E-02 4.040E-02 3.380E-01 3.784E-01 2.793E+00 l 2.000 4.494E-02 6.470E-02 5.308E-01 5.955E-01 3.754E+00 4.000 9.609E-02 1.399E-01 1.089E+00 1.229E+00 6.563E+00 f 8.000 1.605E-01 2.391E-01 1.800E+00 2.039E+00 1.125E+01 24.000 2.252E-01 3.524E-01 2.695E+00 3.047E+00 1.955E+01 96.000 2.505E-01 4.022E-01 3.061E+00 3.463E+00 2.201E+01 720.000 2.639E-01 4.289E-01 3.263E+00 3.692E+00 2.299E+01 i ATD-0190.WPO

cales. r r Control Room Habitability tale. no. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cat. X Safety-Related Non-Safety Related Page 49 of client Commonwealth Edison Company Prepared by Date project Zion Station - Units 1 & 2 Reviewed by oate Proj. No. 9140-41 System No. CR Approved by cate 5.2.3.lb ECCS Leakage Results The control room doses for the ECCS leakage source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM ECCS LEAK FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 1, 1600 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM--- --------

TIME, BODY SKIN SKIN SKIN HOURS GAMMA GAPMA BETA TOTAL THYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.584E-07 2.380E-07 9.313E-07 1.169E-06 7.608E-04 1 .883 8.323E-07 1.251E-06 4.958E-06 6.209E-06 4.377E-03 1.383 2.101E-06 3.160E-06 1.273E-05 1.589E-05 1.226E-02 2.000 3.859E-06 5.806E-06 2.383E-05 2.963E-05 2.512E-02 6.000 1.323E-05 1.995E-05 8.947E-05 1.094E-04 1.313E-01 8.000 1.652E-05 2.494E-05 1.153E-04 1.402E-04 1.856E-01 24.000 2.581E-05 3.910E-05 1.983E-04 2.374E-04 4.322E-01 96.000 3.069E-05 4.666E-05 2.448E-04 2.914E-04 7.390E-01 720.000 3.325E-05 5.067E-05 2.644E-04 3.150E-04 9.937E-01 I 1 1.TD-0190.VPD )

cales. r r Control Room Habitability cale. No. ATD-0190 SARGENT&LUNDY ENGNEN Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Paoe 50 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Pro 1. No. 9140-41 system no. CR Approved by Date 5.2.3.lc Leakage Back to the RWST Results The control room doses for the leakage back to the RWST source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM LEAK TO RWST FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 1, 1600 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GMMA C#MA BETA TOTAL WYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.343E-08 2.018E-08 7.897E-08 9.915E-08 6.451E-05 .883 7.058E-08 1.061E-07 4.204E-07 5.265E-07 3.711E-04 1.383 1.782E-07 2.680E-07 1.079E-06 1.347E-06 1.040E-03 2.000 3.272E-07 4.923E-07 2.021E-06 2.513E-06 2.130E-03 6.000 1.122E-06 1.692E-06 7.587E-06 9.278E-06 1.114E-02 8.000 1.401E-06 2.115E-06 9.774E-06 1.189E-05 1.574E-02 1 24.000 2.189E-06 3.316E-06 1.682E-05 2.013E-05 3.665E-02 96.000 2.602E-06 3.957E-06 2.075E-05 2.471E-05 6.267E-02 720.000 2.820E-06 4.297E-06 2.242E-05 2.671E-05 8.428E-02 i ATD-0190.WP0

SARGENT & LUNDY ENGINEERS Radiological Dose Analysis new. 2 Date X Safety-Related Non-Safety Related Pace 51 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 System No. CR Approved by Date 5.2.3.2 CASE 2,1800 CFM Control Room Makeup Flow Rate 5.2.3.2a Containment Leakage Results The control room doses for the containment 1.eakage source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM CONT. LEAKAGE USING 144 CFM INLEAKAGE TO CONTROL RM. CASE 2, 1800 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAPHA GAPMA BETA TOTAL THYROID

.031 3.119E-05 4.492E-05 3.664E-04 4.113E-04 1.304E-02 .281 2.145E-03 3.079E-03 2.594E-02 2.902E-02 5.302E-01 .338 2.991E-03 4.292E-03 3.631E-02 4.060E-02 6.623E-01 .715 1.071E-02 1.535E-02 1.308E-01 1.462E-01 1.460E+00 .914 1.583E-02 2.269E-02 1.928E-01 2.155E-01 1.839E+00 1.414 3.018E-02 4.332E-02 3.629E-01 4.062E-01 2.693E+00 2.000 4.773E-02 6.871E-02 5.644E-01 6.331E-01 3.575E+00 4.000 9.997E-02 1.456E-01 1.135E+00 1.281E+00 6.115E+00 8.000 1.646E-01 2.450E-01 1.848E+00 2.093E+00 1.036E+01 24.000 2.289E-01 3.576E-01 2.737E+00 3.095E+00 1.783E+01 96.000 2.540E-01 4.072E-01 3.101E+00 3.508E+00 2.004E+01 720.000 2.674E-01 4.338E-01 3.303E+00 3.737E+00 2.092E+01 ATD-0190.VP0

cales. ror Control Room Habitability caic. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 case X Safety-Related Non-Safety Related Page 52 of client Commonwealth Edison Company Prepared by Date l Project Zion Station - Units 1 & 2 Reviewed by Date Pro 1. No. 9140-41 system No. CR Approved by Date l 5.2.3.2b ECCS Leakage Results The control room doses for the ECCS leakage source were: ZION i & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM ECCS LEAK FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 2, 1800 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAPEA GAPMA BETA TOTAL BiYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.591E-07 2.391E-07 9.354E-07 1.174E-06 7.641E-04 .883 8.270E-07 1.243E-06 4.926E-06 6.169E-06 4.347E-03 1.383 2.063E-06 3.103E-06 1.250E-05 1.560E-05 1.203E-02 2.000 3.744E-06 5.634E-06 2.311E-05 2.875E-05 2.433E-02 6.000 1.240E-05 1.870E-05 8.374E-05 1.024E-04 1.223E-01 8.000 1.540E-05 2.324E-05 1.072E-04 1.305E-04 1.716E-01 24.000 2.378E-05 3.603E-05 1.822E-04 2.182E-04 3.945E-01 96.000 2.820E-05 4.288E-05 2.243E-04 2.672E-04 6.729E-01 720.000 3.053E-05 4.652E-05 2.421E-04 2.886E-04 9.041E-01 4 ATD-0190.VP0

cales. F r Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ra a m t ats Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 53 of client Commonwealth Edison Company Prepared by Date pro 3ect Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date 5.2.3.2c Leakage Back to the RWST Results The control room doses for the leakage back to the RWST source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM LEAK TO RWST FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 2, 1800 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAMA GAMA BETA TOTAL THYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.349E-08 2.027E-08 7.931E-08 9.959E-08 6.479E-05 .883 7.012E-08 1.054E-07 4.177E-07 5.231E-07 3.686E-04 1.383 1.750E-07 2.631E-07 1.060E-06 1.323E-06 1.020E-03 2.000 3.175E-07 4.777E-07 1.960E-06 2.438E-06 2.063E-03 6.000 1.052E-06 1.586E-06 7.101E-06 8.687E-06 1.037E-02 8.000 1.306E-06 1.971E-06 9.091E-06 1.106E-05 1.455E-02 24.000 2.017E-06 3.055E-06 1.545E-05 1.850E-05 3.345E-02 96.000 2.392E-06 3.636E-06 1.902E-05 2.266E-05 5.706E-02 720.000 2.589E-06 3.945E-06 2.053E-05 2.447E-05 7.668E-02 4 ATD-0190.VP0

i l' I C* I ~ " ' ^ ~ ' SARGENT & LUNDY i i recrutm Radiological Dose Analysis Revi 2 oate-X Safety-Related Non-Safety Related Pane 54 of client Commonwealth Edison Company Prepared by Date '{ Project Zion Station - Units 1 & 2 Reviewed by oate Prof. No. 9140-41 system No. CR Approved by cas. i 5.2.3.3 CASE 3, 2000 CFM Control Room Makeup Flow Rate t 5.2.3.3a Containment Leakage Results l The control room doses for the containment leakage sourco were: l i ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FRUM CONT. LEAKAGE USING 144 CFM INLEAKAGE TO CONTROL RM. CASE 3, 2000 CFM MAKEUP' FLOW SUM OVER ALL NUCLIDES 9

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN j

HOURS GAMA GAMA BETA TOTAL ]llyROID .031 3.407E-05 4.906E-05 4.020E-04 4.511E-04 1.319E-02. .281 2.333E-03 3.348E-03 2.830E-02 3.164E-02 5.309E-01 .338 3.251E-03 4.662E-03 3.955E-02 4.421E-02 6.616E-01 .715 1.154E-02 1.654E-02 1.411E-01 1.577E-01 1.437E+00 .914 1.699E-02 2.434E-02 2.071E-01 2.314E-01 1.799E+00 l 1.414 3.206E-02 4.602E-02 3.860E-01 4.320E-01 2.599E+00 ) 2.000 5.024E-02 7.232E-02 5.948E-01 6.671E-01 3.411E+00 4.000 1.033E-01 1.504E-01 1.175E+00 1.325E+00 5.728E+00 8.000 1.680E-01 2.500E-01 1.889E+00 2.139E+00 9.604E+00 24.000 2.319E-01 3.619E-01 2.773E+00 3.135E+00 1.641E+01 96.000 2.570E-01 4.ll4E-01 3.136E+00 3.547E+00 1.842E+01 720.000 2.704E-01. 4.380E-01 3.338E+00 3.776E+00 1.924E+01 1 ATD-0190.WP0

C' ' ' " ' SARGENT & LUNDY r.Nostats Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 55 of c uent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Pro 3. no. 9140-41 System No. CR Approved by Date 5.2.3. ? ECCS Leakage Results The control room doses for the ECCS leakage source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM ECCS LEAK FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 3, 2000 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN tERS GA)MA GAPMA BETA TOTAL TIIYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 '0.000E+00 .500 1.598E-07 2.401E-07 9.394E-07 1.179E-06 7.674E-04 .883 8.217E-07 1.235E-06 4.895E-06 6.130E-06 4.318E-03 1.383 2.027E-06 3.048E-06

1. 227E-05 1.532E-05 1.180E-02 2.000 3.637E-06 5.473E-06 2.244E-05 2.792E-05 2.358E-02 6.000 1.169E-05 1.762E-05 7.879E-05 9.641E-05 1.145E-01 8.000 1.444E-05 2.180E-05 1.003E-04 1.221E-04 1.598E-01 24.000 2.209E-05 3.347E-05 1.688E-04 2.023E-04 3.636E-01 96.000 2.615E-05 3.975E-05 2.074E-04 2.472E-04 6.189E-01 720.000 2.828E-05 4.308E-05 2.237E-04 2.668E-04 8.310E-01 ATD-0190.VP0

cales. r r Control Room Habitability calc. No. ATD-0190 SARGENT & LUNDY ENGD4EERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 56 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Revie ed by Date Proj. No. 9140-41 system No. CR Approved by Date 5.2.3.3c Leakage Back to the RWST Results The control room doses for the leakage back to the RWST source were: ZION 1 & 2, PROJ. N0. 9140-41, CONTROL RM DOSES FROM LEAK TO RWST FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 3, 2000 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAMA GAMM BETA TOTAL THYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.355E-08 2.036E-08 7.966E-08 1.000E-07 6.507E-05 .883 6.968E-08 1.047E-07 4.150E-07 5.198E-07 3.661E-04 1.383 1.718E-07 2.584E-07 1.041E-06 1.299E-06 1.001E-03 2.000 3.084E-07 4.640E-07 1.903E-06 2.367E-06 2.000E-03 6.000 9.909E-07 1.494E-06 6.681E-06 8.175E-06 9.710E-03 8.000 1.224E-06 1.848E-06 8.509E-06 1.036E-05 1.355E-02 24.000 1.874E-06 2.838E-06 1.431E-05 1.715E-05 3.083E-02 96.000 2.217E-06 3.370E-06 1.759E-05 2.096E-05 5.248E-02 720.000 2.398E-06 3.653E-06 1.897E-05 2.263E-05 7.048E-02 P 1 ATD-0190 NPD

cales. For Control Room Habitability caic. No. ATD-0190 SARGENT & LUNDY ENGINEN Radiological Dose Analysis Rev. 2 Dat. X Safety-Related Non-Safety Related Pace 57 of client Commonwealth Edison Company Pnepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date l Prof. No. 9140-41 system No. CR Approved by Date ) 5.2.3.4 CASE 4, 2200 CFM Control Room Makeup Flow Rate 5.2.3.4a Containment Leakage Results The control room doses for the containment 1.eakage source were: ZION 1 & 2, PROJ. N0. 9140-41, CONTROL RM DOSES FROM CONT. LEAKAGE USING 144 CFM INLEAKAGE TO CONTROL RM. CASE 4, 2200 CFM MAKEUP FLOW ~ SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAMA GAMA BETA TOTAL THYROID

.031 3.695E-05 5.319E-05 4.375E-04 4.907E-04 1.334E-02 i .281 2.519E-03 3.613E-03 3.060E-02 3.422E-02 5.316E-01 .338 3.504E-03 5.025E-03 4.271E-02 4.774E-02 6.609E-01 .715 1.234E-02 1.768E-02 1.510E-01 1.687E-01 1.416E+00 .914 1.808E-02 2.591E-02 2.206E-01 2.465E-01 1.760E+00 l.414 3.381E-02 4.852E-02 4.073E-01 4.558E-01 2.511E+00 2.000 5.252E-02 7.559E-02 6.223E-01 6.979E-01 3.262E+00 4.000 1.062E-01 1.546E-01 1.209E+00 1.364E+00 5.391E+00 l 8.000 1.710E-01 2.543E-01 1.924E+00 2.178E+00 8.967E+00 24.000 2.346E-01 3.657E-01 2.805E+00 3.171E+00 1.523E+01 96.000 2.596E-01 4.150E-01 3.166E+00 3.581E+00 1.708E+01 720.000 2.729E-01 4.416E-01 3.368E+00 3.810E+00 1.784E+01 ATD-0190.VP0

cales. r r Control Room Habitability caic. No. ATD-0190 SARGENT & LUNDY EMMEM Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Pace 58 of client Commonwealth Edison Company Prepared by Date Pro ject Zion Station - Units 1 & 2 Reviewed by Date ProJ. No. 9140-41 System No. CR Accroved or Date 5.2.3.4b ECCS Leakage Results The control room doses for the ECCS leaka9e source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM ECCS LEAK FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 4, 2200 CFM MAKEUP FLOW SLM OVER ALL NUCLIDES

_-INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAPMA GA>MA BETA TOTAL THYROID

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.605E-07 2.411E-07 9.433E-07 1.184E-06 7.705E-04 .883 8.165E-07 1.227E-06 4.863E-06 6.091E-06 4.289E-03 1.383 1.992E-06 2.995E-06 1.206E-05 1.505E-05 1.159E-02 2.000 3.537E-06 5.321E-06 2.182E-05 2.714E-05 2.289E-02 6.000 1.106E-05 1.668E-05 7.447E-05 9.115E-05 1.078E-01 8.000 1.361E-05 2.054E-05 9.443E-05 1.150E-04 1.497E-01 24.000 2.067E-05 3.130E-05 1.576E-04 1.889E-04 3.377E-01 96.000 2.441E-05 3.711E-05 1.933E-04 2.304E-04 5.739E-01 720.000 2.639E-05 4.020E-05 2.084E-04 2.485E-04 7.702E-01 ATD-0193.VPD

ga. F r Control Room Habitability cale. no. ATD-0190 SARGENT & LUNDY ENGINEI~d Radiclogical Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Paoe 59 of client Commonwealth Edison Company Prew red by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system no. CR Approved by cate 5.2.3.4c Leakage Back to the RWST Results The control room doses for the leakage back to the RWST source were: ZION 1 & 2, PROJ. NO. 9140-41, CONTROL RM DOSES FROM LEAK TO RWST FOR 144 CFM INLEAKAGE TO CONTROL RM. CASE 4, 2200 CFM MAKEUP FLOW SUM OVER ALL NUCLIDES

INSIDE CONTROL ROOM DOSE, REM------------

TIME, BODY SKIN SKIN SKIN HOURS GAPMA GAPMA BETA TOTAL THYROID __

.250 0.000E+00 0.000E+00 0.000E+00 0.000E+00 0.000E+00 .500 1.361E-08 2.044E-08 7.999E-08 1.004E-07 6.534E-05 .883 6.924E-08 1.041E-07 4.124E-07 5.165E-07 3.637E-04 1.383 1.689E-07 2.539E-07 1.022E-06 1.276E-06 9.824E-04 2.000 2.999E-07 4.512E-07 1.850E-06 2.301E 06 1.941E-03 6.000 9.379E-07 1.414E-06 6.315E-06 7.729E-06 9.138E-03 8.000 1.154E-06 1.742E-06 8.007E-06 9.749E-06 1.270E-02 24.000 1.752E-06 2.654E-06 1.336E-05 1.601E-05 2.864E-02 96.000 2.070E-06 3.147E-06 1.639E-05 1.95aE-05 4.867E-02 720.000 2.238E-06 3.409E-06 1.767E-05 2.108E-05 6.532E-02 AID-0190 NPD

cales. r r Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGNEDtS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page C0 g client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Pro 1. No. 9140-41 System No. CR Aporoved by Date 5.3 Total 720 Hour Doses From All Leakage Paths for 144 cfm Inleakage The 30-day post-LOCA (i.e. 720 hour) doses to control room personnel are the sum of the dose contributions due to containment leakage, due to ECCS leakage, and due to RWST leakage. Control room total dose contributions from the three leakage paths for each of the four control room makeup air flow rate cases are given in Subsection 5.2.3. Total doses are provided in Table 8. Table 8 r 30 Day Control Room Doses for 144 cfm Unfiltered Inleakage CASE 1: 1600 cfm Makeuo Air Flow Rate 30-DAY DOSE INSIDE CONTROL ROOM (Rem) LEAKAGE WHOLE BODY SKIN SKIN SKIN SOURCE GAMA GAMA BETA TOTAL TliYROID Containment 2.639E-01 4.289E-01 3.263E+00 3.692E+00 2.299E+01 ECCS 3.325E-05 5.067E-05 2.644E-04 3.150E-04 9.937E-01 j Back to RWST 2.820E-06 4.297E-06 2.242E-05 2.671E-05 8.428E-02 TOTAL 2.639E-01 4.290E-01 3.263E+00 3.692E+00 2.407E+01 ATD-0190.WP0 I

cal s. F r n m a a y tale N.A - 90 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 61 of client Commonwealth Edison Company Prepared by Date pro 3ect Zion Station - Units 1 & 2 Revie ed by cate proj. no. 9140-41 system no. CR Approved by Date Table 8 (Cont'd) 30-Day Control Room Doses for 144 cfm Unfiltered Inleakage CASE 2: 1800 cfm Makeuo Air Flow Rate 30-DAY DOSE INSIDE CONTROL ROOM (Rem) LEAKAGE WHOLE BODY SKIN SKIN SKIN SOURCE GAMA GAMA BETA TOTAL THYROID Containment 2.674E-01 4.338E-01 3.303Edo 3.737E+00 2.092E+01 ECCS 3.053E-05 4.652E-05 2.421E-04 2.886E-04 9.041E-01 Back to RWST 2.589E-06 3.945E-06 2.053E-05 2.447E-05 7.668E-02 Total 2.674E-01 4.339E-01 3.303E+00 3.737E+00 2.190Ed1 ATD-0190,VP0

'I SARGENT & LUNDY ENGMEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Pace 62 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by oat. Pro j. No. 9140-41 System No. CR Approved by Date Table 8' (Cont'd) 30-Day Control Room Doses for 144 cfm Unfiltered Inleakage CASE 3: 2000 cfm Makeuo Air Flow Rate 30-DAY DOSE INSIDE CONTROL ROON (Rem) LEAKAGE WHOLE BODY SKIN SKIN-SKIN SOURCE GAMA GAMA BETA TOTAL THYROID Containment 7.704E-01 4.380E-01 3.338E+00 3.776E+00 1.924E+01 ECCS 2.828E-05 4.308E-05 2.237E-04 2.668E-04 8.310E-01 Back to RWST 2.398E-06 3.653E-06 1.897E-05 2.263E-05 7.048E-02 l Total 2.704E-01 4.380E-01 3.338E+00 3.776E+00 2.014E+01 ATD-0190.VP0

Y 'I'~"~^ SARGENT & LUNDY ENGNE N Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 63 of client Commonwealth Edison Company Preparsd by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date Table 8 (Cont'd) 30-Day Control Room Doses for 144 cfm Unfiltered Inleakage CASE 4: 2200 cfm Makeup Air Flow Rate 30-DAY DOSE INSIDE CONTROL ROOM (Rem) LEAKAGE WHOLE 80DY SKIN SKIN SKIN SOURCE GAMMA GMMA 8 ETA TOTAL THYROID r Containment 2.729E-01 4.416E-01 3.368E+00 3.810E+00 1.744E+01 ECCS 2.639E-05 4.020E-05 2.084E-04 2.485E-04 7.702E-01 Back to RWST 2.238E-06 3.409E-06 1.767E-05 2.108E-05 6.532E-02 Total 2.729E-01 4.416E-01 3.368E+00 3.810E+00 1.868E+01 ATD-0190.VP0

cales. F r Control Room Habitability tale. No. ATD-0190 SARGENT & LUNDY ENGMEERS Radiological Dose Analysis Rev. 2 Date i X Safety-Related Non-Safety Related Pace 64 of l client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 system No. CR Approved by Date 5.4 Thyroid Doses for Other Unfiltered Inleakages The thyroid dose, D (rem) for an unfiltered inleakage, f (cfm), can be determined if the thyroid dose, DO (rem), for a specified unfiltered inleakage, f0 (cfm) is known. The dose is inversely proportional to the iodine protection factor (IPF) given by Equations la through Id in Section 4. D0 * [(IPF) for D0] = D * [(IPF) for 0]. Solving for D, D - D0 * [(IPF) for D0] / [(IPF) for D]. EQN.3 Equation 3 is used to determine the 30-day thyroid dose (D) to control room occupants for a specified amount of unfiltered inleakage. The iodi.ne protection factor (IPF) values are determined via equations la through Id. Rearranging gives, l(IPF) for D) l (IPF) for Do] EON. 4 = Equation 4 is used to determine the iodine protection factor (IPF) for the situation when the control room thyroid dose (D) is set equal to the Regulatory limit of 30 rem. Knowing the IPF value, the amount of allowable unfiltered inleakage associated with the 30 rem thyroid dose is then determined via equations la through Id for cases 1 through 4, respectively. Cases 1 through 4 refer to the control room makeup air flow rates. i Table 9 presents the calculation of thyroid doses for the unfiltered inleakage values given in Table 4. Thyroid doses are given for the four cases representing the four control room makeup air flow rate values. Table 9 also provides the calculated amount of allowable unfiltered inleakage to the control room in order to obtain a 30-day thyroid dose equal to the Regulatory limit value of 30 rem. ATD-0190.WPD

G6 o w a a e o g 4, Table 9 E a o o m ~ Z e d p [ 30-Day Thyroid Dose for Table 4 Unfiltered Inleakages { IPF Based On M Unflitered inleakage 3 y g2 g M C Unfiltered Unfiltered inleakage Value of f Control Rome Thyroid Dose W to Inleakage Source f (cre) (i.e.. IPF for D) IPF for Do D (Rem) e E "r i rn Case 1: 1600 cfm Makeup Air Flow Rate, fo = 144 cfm, Do = 24.07 Rem (Table 8) S g R x c i 3. S = [ C E = Minless for Train B 81 (Table 4) 17.33 (Egn. la) 10.90 (Eqn. la) 15.14 (Eqn. 3) p j 9 d h Minta m for Train A 96 (Table 4) 15.14 (Eqn. la) 10.90(Eqn.la) 17.33 (Eqn. 3) 9 Q w a Nxima for Train 8 119 (Table 4) 12.73 (Egn. la) 10.90 (Egn. la) 20.61 (Egn. 3) b w Q n O O l huim a for Train A 144 (Table 4) 10.90 (Egn. la) 10.90 (Egn. la) 24.07 (Table 8) o a For 30 rem Reg. Limit 188.4 (Egn la) 8.75 (Egn. 4) 10.90 (Eqn. la) 30 (Reg. Limit) o" E 8 c Case 2: 1800 cfm Makeup Air Flow Rate, fo = 144 cfm, Do = 21.90 Rem (Table 8) y = E a F B, e o m e 4 a m Minimse for Train B 81 (Table 4) 19.00 (Eqn. Ib) 12.00 (Eqn. Ib) 13.83 (Eqn. 3) E E E h 5 ,+* Minium for Train A 96 (Table 4) 16.63 (Eqn. Ib) 12.00 (Eqn. Ib) 15.80 (Egn. 3) ,= b xim a for Train 8 119 (Table 4) 14.01 (Eqn. Ib) 12.00 (Eqn. Ib) 18.76 (Egn. 3) { h uim e for Train A 144 (Table 4) 12.00 (Egn. Ib) 12.00(Eqn.Ib) 21.90(Table 8) E For 30 rue Reg. Limit 211.6 (Eqn. Ib) 8.76 (Eqn. 4) 12.00 (Eqn. Ib) 30 (Reg. Limit) C 2 n' 5 -4 S ? ? o o o k k k 8 t e O l l t (

e? m n m E a a r x x k Table 9 (Cont'd) a C ~ g ,o m2 -1 30-Day Thyroid Dose for Table 4 Unfiltered Inleakages 3 y p g h IPF Based on Unfiltered Inleakage 3 g gZ Unfiltered Unfiltered inleakage Value of f Control Room Thyrold Dose n' to Inleakage Source f(cfm) (i.e.. IPF for D) IPF for Do D (Ress) g-a to 3 =r l r, Case 3: 2000 cfm Makeup Air Flow Rate, fo = 144 cfm. Do = 20.14 Rem (Table 8) y E o-x c: l T 8 0 l hMininum for Train B l E g 81 (Table 4) 20.60 (Eqn. Ic) 13.07 (Eqn. Ic) 12.78 (Eqn. 3) p j d h Minim a for Train A 96 (Table 4) 18.07 (Eqn. Ic) 13.07(Eqn.Ic) 14.57(Eqn.3) e os a os Maxisua for Train B 119 (Table 4) 15.24 (Eqn. Ic) 13.07 (Eqn. Ic) 17.27 (Egn. 3) O 3 y Q CL C3 o Maxinue for Train A 144 (Table 4) 13.07 (Egn. Ic) 13.07 (Eqn. Ic) 20.14 (lable 8) o a For 30 resa Reg. Limit 234.8 (Eqn Ic) 8.77 (Egn. 4) 13.07 (Eqn. Ic) 30 (Reg. Lleft) o" F g b Case 4: 2200 cfm Makeup Air Flow Rate, fo = 144 cim, Do = 18.67 Ram (Table 8) -y x as 8, 3 a E E a-o a m e 2 7 a os Mintsue for Train B 81 (Table 4) 22.15 (Eqn. Id) 14.12 (Eqn. Id) 11.91(Eqn.3) E E E h 5 a a a ~ Minlaus for Train A 96 (Table 4) 19.46 (Eqn. Id) 14.12 (Eqn. Id) 13.55 (Eqn. 3) m a Maxim a for Train B 119 (Table 4) 16.45 (Eqn. Id) 14.12.(Egn. Id) 16.03 (Eqn. 3) { Marium for Train A 144 (Table 4) 14.12 (Egn. Id) 14.lf (Egn. Id) 18.68 (Table 8) E For 30 ress Reg. Limit 257.6 (Eqn. Id) 8.79 (Eqn. 4) 14.12 (Eqn. Id) 30 (Reg. Limit) m m n n v S- ? o o o k k I 8 8

cales. r r Control Room Habitability tale. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 67 of i Client Commonwealth Edison Company prepared by cate Pro 3ect Zion Station - Units 1 & 2 Reviewed by oate Prof. No. 9140-41 System No. CR Approved by cate 6. RESULTS Table 10, which follows, provides a summary of control room doses as a function of unfiltered inleakage for the four makeup air flow rates addressed via this calculation. Postaccident dose limits to control room personnel, given in GDC 19 to Appendix A of 10 CFR 50, are also listed in Table 10 to. enable comparison of calculated doses to regulatory limit values. 1 ATo-0190.WP0

Cales. F r Control Room Habitability Calc. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 68 of l citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 Syst m No. CR Approved by Date Table 10 30-Day Control Room Doses and Comparison with Regulatory Limits CASE 1: 1600 cfm MakeuD Air Flow Rate unfiltered Inleakage 30-Day Control Room Doses Rate Whole Body Skin Thyroid source (cfa) (Ram) (Rm) (Rm) Train 8 Mininum 81 15.1 Train A Minimum 96 17.3 Train B Maximaan 119 20.6 Train A Maximum 144 0.264 3.C9 24.1 30 rem Regulatory Limit 188.4 30.0 10 CTR 50. App. A, GDC 19 5.0 30.0 30.0 CASE 2: 1800 cfm Makeun Air Flow Rate Unfiltered Inteakage 30-Day Control Room Doses Rate Whole Body skin Thyroid source (cfs) (Rem) (Ras) (Ran) Train 8 Minimum 81 13.8 Train A Minimum 96 15.8 Train B Maximass 119 18.8 Train A Maximaan 144 0.267 3.74 21.9 30 rm Regulatory Limit 211.6 30.0 10 CFR 50 App. A, GDC 19 5.0 30.0 30.0

Per Engineering Judgement #3 in Section 3 to this calculation, this dose value is smaller than the corresponding dose value given for the unfiltered inleakage rate of 144 cfm.

ATO-0190.WP0

tales. F r Control Room Habitability Calc. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Page 69 of ciient Commonwealth Edison Company Prepared by Date Pro ject Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by Date Table 10 (Cont'd) 30-Day Control Room Doses and Comparison with Regulatory Limits CASE 3: 2000 cfm Makeuo Air Flow Rate unfiltered Inleakage 30-Day Contrr,1 Roan Doses Rate Whole Body Skin Thyroid Source (cfa) (Rem) (Ram) (Rem) Train B Minisue 81 12.8 Train A Minisue 96 14.6 Train B Maximum 119 17.3 Train A Maximum 144 0.270 3.78 20.1 30 ras Regulatory Limit 234.8 30.0 10 CFR 50. App. A. GDC 19 5.0 30.0 30.0 CASE 4: 2200 cfm Makeuo Air Flow Rate Unfiltered Inleakage 30-Day Control Room Doses Rate Whole Body Skin Thyroid Source (cfe) (Rem) (Rem) (Rau) Train B Minimum 81 11.9 Train A Minimum 96 13.6 Train B Kaxious 119 16.0 Train A Maximus 144 0.273 3.81 18.7 30 rea Regulatory Limit 257.6 30.0 10 CFR 50, App. A, GDC 19 5.0 30.0 30.0

Per Engineering Judgement #3 in Section 3 to this calculation, this dose value is smaller than the corresponding dose value given for the unfiltered inleakage rate of 144 cfm.

ATD-0190.VP0

1 C*** Y '*I * " ' ~ SARGENT & LUNDY ENGWEERS Radiological Dose Analysis Rev. 2 Date X Safety-Related Non-Safety Related Paae 70 of Client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Cate prof. No. 9140-41 system No. CR Approved by Date Based on the results presented in Table 10, it is seen that the control room doses are below regulatory limits for the four makeup air flow rates and the associated unfiltered inleakage rates analyzed in this calculation. i l i l ATD-0190,WP0 I

'I " ' ~ SARGENT & LUNDY ENGWEEM Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 71 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 System No. CR Approved by oate 7. REFERENCES 1. U. S. Nuclear Regulatory Commission, " Assumptions Used for Eyaluating the Potential Radiological Consequences of a Loss of Coolant Accident for Pressurized Water Reactors," USNRC Regulatory Guide 1.4, Rev. 2, June 1974. 2. Commonwealth Edison Company, Zion Station, Units 1 and.2, Updated FSAR, June 1992. 3. W. T. Perchiazzi, Commonwealth Edison Company, " Additional Support Information For Control Room Habitability Dose Calculation," Letter to G. P. Lahti, Sargent and Lundy, Dated October 26,1992, Chron # 193548, See Attachment Number 4. 4. Letter from W. T. Perchiazzi and P. R. Donavin to G. P. Lahti, " Revision to Control Room Habitability Dose Evaluation for Zion Station, S&L Calculaton ATD-190, Revision 1," dated January 19, 1993, Chron #197219. See Attachment Number 5. 5. Reactor Containment Ventilation Systems Functional Description, FD-RV-01, Rev. 8, January 28, 1987. 6. R. S. Hubner, " Control Room Doses From Inside Atmosphere After LOCA," Sargent & Lundy Calc. No. ZI-THI-Al-5, Rev. O, for Commonwealth Edison Company, September 5, 1980. 7. Zion Station, Technical Specifications, Appendix A, Subsection 3.10.1.A.I.a.

p. 212 of Operating License.

8. U. S. Nuclear Regulatory Commission, 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," NUREG-0800, Rev.1, July 1981. ATo-0190.VP0

cales. F r Control Room Habitability cale. No. ATD-0190 SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 oate X Safety-Related Non-Safety Related Page 72 of citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj, No. 9140-41 system No. CR Approved by Date 9. W. T. Perchiazzi, Commonwealth Edison Company, " Transmittal of Testing Information to Be Used in Control Room Habitability Dose Analysis," Letter to G. P. Lahti, Sargent and Lundy, Dated September 30, 1992, Chron # 192445, See Attachment Number 2. 10. B. C. Schwartz, Sargent and Lundy, " Notes of Meeting February 25, 1992, Held in Commonwealth Edison's Zion Station Offices," File No. 4.6, See Attachment Number 3. 11. S. Dhall and J. S. Reda, " Containment Spray Flow Evaluation Using the RHR Pump," Sargent and Lundy, MAD, Calc. No. 91-0083, for Commonwealth Edison Company, June 24, 1991. 12. R. S. Hubner, " Control Room Infiltration Study," Sargent and Lundy, ATD, Calc. No. ZI-5-91, Rev. O, for Commonwealth Edison Company, April 23, 1991. 13. U. S. Nuclear Regulatory Commission, Standard Review Plan, Section 6.5.2, " Containment Spray as a Fission Product Cleanup System," NUREG-0800, Rev. 2, December 1988. 14. W. J. Adams, Sargent and Lundy, " Control Room Volume and Air Change Rate," DIT No. ZI-HVAC-0040-00, January 18, 1991. 15. ATD Calculation #ATD-0214, " Containment Sprayed Volume Analysis," Rev. 0,_ January 28, 1993. 16. G. P. Lahti, "X/Q for Postaccident Control Room Habitability Calculations," Sargent and Lundy, ATD, Calc. No. ATD-0194, Rev. O, for Commonwealth Edison Company, October 28, 1992. 17. K. G. Murphy and K. M. Campe, " Nuclear Power Plant Control Room Ventilation System Design for Meeting General Criterion 19," 13th AEC Air Cleaning Conference, August 1974. ATD-0190.VP0

'I* Y C*I* " ' ^ ' SARGENT & LUNDY ENGINEERS Radiological Dose Analysis Rev. 2 cate X Safety-Related hon-Safety Related Page 73 of citent Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Prof. No. 9140-41 System No. CR Aporoved by Date 18. Federal Guidance Report No,11, " Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," EPA-520/1-88-020, September 1988. 19. U. S. Nuclear Regulatory Commission, Standard Review Plan, Section 6.4, " Control Room Habitability System," NUREG-0800, Rev. 2, July 1981. 20. R. S. Hubner, Sargent and Lundy, "PWR Power Plant Dose After DBA Code," User's Manual for POSTDBA, Program No. 03.7.287-1.0, August 19, 1991. 21. ATD Calculation #ATD-0206, Organic Iodine Recirculation Spray Removal Rate," Rev. 1, February 17, 1993.' 22. Letter from Bill Perchiazzi and Bob Rybak to G. P. Lahti, " Zion Control Room ~ Habitability Dose Evaluation," dated March 5,1993, Chron #198864. See Attachment Number 6. ATD-0190.WP0 1

SARGENT & LUNDY - cales. r n m Ha aW Hy Calc. No. MD-0B0 mG5m8 Radiological Dose Analysis Rev. 2 cate X Safety-Related Non-Safety Related Page 74 of client Commonwealth Edison Company Prepared by Date Project Zion Station - Units 1 & 2 Reviewed by Date Proj. No. 9140-41 system ho. CR Acoroved by Date ATTACHMENT 1 Microfiche of POSTDBA Input and OUTPUT E l ATD-0190.VP0

7 /c m-_)'Commonweaitn Ecison 2., ( 7' {My,~3 6 - s E= i ATTACHMENT 2 (Page 1 of.3) Septencer 30, 1992 In Reply Refer to Chron # 192445 Gerald Lahti Calc. No. ATD-0190-Sargent & Lundy Engineers Rev. 2 Proj. No. 9140-41 55 E. Monroe Chicago, Il 60603 Page 75 Transmittal of Testing Information to be used in

Subject:

Control Room Habitability Dose Analysis

References:

Lagus Applied Technology with Appendix, Inc Report dated 1. April 15, 1992 2. Lagus Applied Technology, Inc Report dated July 15, 1992 3. Lagus Applied Technology, Inc Report dated June 26, 1992 4. Zion P&ID's M-64, M-62 5. Zion UFSAR Section 6.3.2.2.5.2 6. Zion UFSAR Section 6.3.2.2.5.5 7. Velan Drawing 137.116-1 for SI MOV's 8. Specification X-3646 Piping Design Tables 9. Cermak Peterka Petersen (CPP), Inc Wind Tunnel Testing Report' for Zion Station Dated March 2, 1992 S&L DIT-21-EXT-307 Dated March 25, 1992 10. NFS Letter NFS:RSA:92-050 CHRON # 184271 11.

Dear Mr. Lahti:

The purpose of this letter is to transmit the information.on testing completed at Zion Station for Control Room Boundary Inleakage and Dilution Testing performed by the station with the support of Lagus Technologies. The Inleakage results from the testing completed and submitted in Reference 1 are as follows: Train B Train A 181 1 34 CFM. 156 1 27 CFM Additional testing completed and submitted in Reference 2 has.the inleakage reduced to the following numbers: Train B Train A 120 2 24 CFM 100 : 19 CFM For the dose calculation use the above inleakage values from the latest test report of Juli 15, 1992.

a ATTACHMENT 2 (Page 2 of 3) Calc. No. ATD-0190 ! Rev. 2 Proj. No. 914 0-41 Page 76 The CPP test report data (Reference 9) shall be used in determination of the actual X/Q. The dilution factor for the air transport from the diesel intake to the Control Room Air PV Filter unit intake was determined from testing completed in March of 1992. Reference 3 indicates a dilution factor of 1.61 1 11 can be used for the air path from the EDG intake to the Control Room PV Filter unit intake. The potential leakage back to the RWST identified in Information Notice 91-56 also needs to be included in the analysis. The station measured leakage back to the RWST during the SI full flow testing and could not identify any such leakage. However, as a conservative measure some leakage value should be used to ensure that if leakage does occur, the dose to the control room operators is not significantly affected. The Safety Injection recirculation valves back to the RWST are closed during the event and only opened during testing of the SI Pumps. The leakage through these valves is considered minimal. Reference 5 states the motor operated valves are considered to be leak tight. Reference 6 specifies the leakage limitations associated with various types of valves in the ECCS systems. The Motor operated valves are 1500 LB valves per Reference 7. The leakage limit for the motor operated valves (Reference 6, Number 3) specified is 3 cc/ Hr/in of nominal pipe size. The pipe size associated with these valves is 2 inch. The manual valve SI8735, is in line ISIOO3-3" L-R. Reference 8 piping design table for this pipe class indicated the valve to be a class 600. The leakage limitation from Reference 6 for this manual gate valve is 3 cc/Hr/in of nominal pipe size. The line size associated with this valve is 8 inch. In summary, the following values should be used for leakage back to the RWST during the Recirculation phase of the LOCA and continuing for the duration of the event: SI8735 24 cc/Hr MOV SI8813, 8814 6 cc/Hr The containment Spray (CS) system will be operated for four days following the event. The calculation should assume that the CS system will be operated for four days following the LOCA. The EOP revision to ensure the CS system operation will continue for four days is being developed by Site Engineering with the station. Also as discussed, it shall be the assumed delay for CS system actuation is 110 Seconds per References 10 and 11.

ATTACHMENT ~ 2 (Page 3'of 3) Calc. No. ATD-0190 - Rev. 2 - ~ 9140-41? I Proj. No. Page 77: The above.information is approved for use in the S&L. Analysis for i Control Habitability..If you have any questions contact William f T. Perchiazzi at 708-515-7690 in Downers Grove. y / // "U Prepared by: _ d /#( h ' / /lM-wuv William T. Perchiazzf . Mechanical:& Structural Design.. Engineering ~ Reviewed by:. 1 L. J. Corts Mechanical & Structural Design Engineering Approved by: [/ - 9[No/93- ~ P.R. Dofifvfn Mechanical & Structural Design Engineering Supervisor ~) cc: K. Ainger Zion L. Dubois Zion M. Burns Zion J. Ewald PWR Systems B. Adams Zion B. Schwartz S&L D. Flens S&L NEDCC i a l i 5 .i

SARGENT & LUNDY j E N gin E EQ$ CMICOGO f ATTACHMENT 3 (Page 1 of 3) Project No. 8986-10 i File No. 4.6 Commonwealth Edison Company Zion Station Calc. No. ATD-0190-, Notes of Meeting February 25, 1992 .Rev.-2 Held in Commonwealth Edison's Proj. No. 9140-41 Zion: Station Offices Page.78 ~ [ THOSE PRESENT ,i R. Adams ) R. E. Lane ) Commonwealth Edison Company (Ceco) N. A. Valos ) Zion Station l S. Berczynski ) Commonwealth Edison Company (Ceco) [ ENC-G. P. Lahti ) Sargent & Lundy (S&L) 'i B. C. Schwartz ) Purcose: q The purpose of'this meeting was to discuss the post-LOCA containment' spray 1' scenario used in S&L's control room habitability analysis and to confirm this -spray scenario is consistent with station operating procedures or amend the scenario used by S&L as apprcpriate. j Iniection Phase of Containment Soray Two containment spray scenarios were discussed: Original FSAR 6A-9 and original FSAR 6.2-9. Ceco Zion personnel in attendance agreed that the following containment spray scenario is consistent with station E0Ps. See. attached diagram. ECCS and 2 containment spray pumps are operating (assures 1 active failure, a CS pump fails to start). With two (2) CS pumps operating the containment spray flow rate is 5230 gpm. The first low level alarm (low:setpoint) is at 13'6" (140,000 .j gallons) in the RWST. At this level,. change over for recirculation begins. At the lowLlow setpoint (100,000 ~ gallons), 9'10" in'the RWST, all pumps'taking suction from the RWST.are stopped except for l' t containment spray pump. March 25, 1992 o 'I ?

ATTACHMENT 3 (Page 2 of 3) Commonwealth Edison Company March 25, 1992 Zion Station Project No. 8986-10 Page 2 Notes of Meeting February 25, 1992 calc. No. ATD-0190 Held in Commonwealth Edison's Rev. 2 Zion Station Offices Proj. No. 9140-41 Page 79 In.iection Phase of Containment Soray (cont'd) One containment spray pump continues to operate until the RWST is e empty. S&L noted this scenario is consistent with the spray scenario used in S&L's control room habitability calculation. Therefore, the containment spray calculation in S&L's calculation is consistent with the station's present-E0Ps. Recirculation Phase of Containment Soray S&L stated that a valve realignment time of 30 minutes after the RWST tank is empty had been previously given by Ceco ENC for initiating containment spray in the Recirc mode using the RHR pump. CECO-Zion personnel stated that the 30 minute value was conservative, but the station could procedurally defend 15 minutes. For the period of time allotted for valve realignment, there would be no iodine removal via the containment spray. Ceco-ENC requested that S&L make a preliminary evaluation of the impact on control room doses of the 15 minute time differential in reinitiating the containment spray via the RHR pump. ~ rts) A / B. C. SchwarJr BCS: erb Attachment Copies: K. A. Ainger W. C. Cleff/J. L. Tenwinkle L. J. DuBois R. A. Hameetman T. P. Joyce N. Weber A. D. Miosi J. Gering L. M. Simon R. S. Hubner CECO Chron System R. S. Kalita L. J. Barrett R. J. Skowzgird C. M. Chiappetta J. S. Steele K. T. Kostal Meeting Attendees P. L. Wattelet File 4.6 ATD File c: \\mtgnotes\\bes t.ero

C ics.Fer Case.No.f Q.){*O I SARGENT&LUNDY n -ATTAcHMEMT 3 (Page-3 of 3 i Rev. 2 l Dete l $3lggy.Related . ll. l Non-Safety.Related Pege 80 'ot ENGINEERBU Cilent Prepared by Dele Project Reviewed by Date l Date Pro l. No. 9140-41 Eculp. No. Approved by q ~! 3IO 000 o c. / 3.fO 000 G en. / .e s s TAIJEc 1L. ora PHns E ECC.5 jalv s j d C.$ vMfS ,5 CQ f ( re Cafc. "t5 30 3fM c%gou sfut 1St low level

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9'/o" lata ha skt Pf.

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Calc No.. ATD-0190 ~ Revision: 2 Project No.: 9140-41 Page No.: 81 Safety Related October 26, 1992 Atta@ent 4 (Page 1 of 2) In Reply Refer to Chron # 193548 To: Gerald Lahti, Sargent & Lundy Engineers

Subject:

Additional Support Information For Control Room Habitability Dose Calculation During the preparation of the subject analysis, there are still some unresolved items which need to be addressed. 1. The spray Droplet Height for the containment Spray is given in UFSAR Table 6B-1 of 147 Feet. 2. The Filter Unit make up flow to be used is 1600 CFM. The original design flow is 2000 CFM, however due to system pressure losses, the system can not meet the design flow rate of 2000 +/- 10% CFM. The system acceptance criteria will be to ensure a flow greater than 1600 CFM but less than the filter unit maximum flow of 2200CFM(+10%). As discussed, the lower the number in this.casn will yield the conservative dose assessment. 3. The Auxiliary building filter unit efficiency is to be taken as 90%. This is acceptable since Technical Specification 3.17 requires the in place test to have a bypass of less than.05% and a lab test of less than 5% Penetration. This testing exceeds the requirements for 90% acceptance criteria specified in Reg Guide 1.52 and the testing' requirements-specified in Generic Letter 83-13. The later of the sources indicates that a 1% Bypass is acceptable and a 10% Lab Test is acceptable for a 90% Efficiency to be used in dose assessments. 4. The percent Containment Spray Volume to be used is not provided in the UFSAR. A Value of 85% may be used due to the fact that the analysis assumes that the containment fan coolers are running. SRP 6.5.2 states that it is.a valid assumption provided containment ventilation is operating and the system design provides for a sprayed area of i approximately 90%. In addition, the Byron and Braidwood analysis uses a spayed volume of 92%. Therefore, the use of j 85% would be considered acceptable. l The above information is acceptable for use in the control room habitability dose analysis. l i I

1 (Page 2 of 2) If you have any questions, con *act Bill Perchiazzi at 708-515-7690. Prepared By: D William T. Perchiazzf' Mechanical and Structural Design Engineer Calc No.: ATD-0190 ./ Revision: 2 fo /24/#2, Project No.: 9140-41 Reviewed by: Page No.: 82 L. J. Corts Mechanical and Structural Safety Related Design Approved by: wow /v/p 7/f;7 paul R. Donavin Mechanical and Structural Design Supervisor cc: B. Schwartz S&L D. Flens S&L R. Hubner S&L NEDCC i i i

ATTACHMENT 5 (Page 1 of 1) eh*. fD-0190 a O Downers Grove, Illinois 60515 Commonwealth Edis n 1400 Opus Place Pro 3. No. 9140-41 Pace 83 Safety Related January 19, 1993 In Reply Refer to Chron # 197210 Gerald Lahti, Sargent and Lundy Engineers

Subject:

Revision to Control Room Habitability Dose Evaluation for Zion Station, S&L Calculation ATD-190, Revision 1 The purpose of this letter is to provide the information required as additional input for the Calculation Revision. Per our discussions, Commonwealth Edison is requesting the dose evaluation be revised to include the calculated sprayed versus unsprayed containment volume from S&L calculation ATD-214 Rev 0 and the Organic Iodine Recirculation Spray Removal Rates from S&L Calculation ATD-0206, Rev 0. In addition Commonwealth Edison would like the dose calculation to be performed using the 1600 CFM makeup filter unit flow as previously transmitted. In addition, CECO is requesting the dose be evaluated at 1800 CFM, 2000 CFM and 2200,CFM. The calculation should also determine tihe maximum unfilte$ed inleakage allowable with each of the above flow rates. 708-663-If you have any questions contact Bill Perchiazzi at 7690. / 4 W d u [.c[c d h William T. Perchiazti Mechanical and Structural Design Engineering k / & A /ho/93 Paul R. Donavin Mechanical and Structural Design Engineering Supervisor cc: K. A. Ainger Zion ENC L. Dubois Zion Tech Staff D. Flens S&L NEDCC

Calc. No. : ATD-0190 r'%) 1400 Opus Placa Rev No.

2-C:mm:nw cith Edis:n

( Proj. No. : 9140-41 1 1 ',_"mv/ Downers Grove, Illinois 60515 Page No.

84 Safety-Related March 5, 1993 In-Reply Refer to Chron #

198864 ATTACHMENT 6 (Page 1 of 1) Gerald P. Lahti, Sargent & Lundy Engineers i

Subject:

Zion Control Room Habitability Dose Evaluation ) i The subject evaluation is currently being finalized by Sargent.& Lundy. Recently, the station informed Engineering that the removal of the Boron Injection Tank (BIT) for both units has been completed. The modifications which removed the BIT tanks was M22-1/2-88-021. The BIT tank volume is an input for the dose evaluation. Engineering is requesting Sargent & Lundy to incorporate the removal of the BIT tank in the current dose evaluation being performed. Per discussions with you and Bill Perchiazzi, this will,not affect the current budget _or schedule for this' project'. F If you have any questions please contact Bill Perchiazzi at 708-663-7690. /G J7,r).f l , KwW Bill Perchiazzi Mechanical & Structural Design Engineering 1 Bob Rybak Mechanical & ructural Design Engineering Supervisor cc: K. Ainger Zion ENC L. Dubois Zion Station M. Burns Zion Tech Staff NEDCC File = Doses I 1 i h-

Calc. No. ATD-0190 REVIEW METHOD SHEET Revision 2 Page 85 Proj. No. 8986-10 SAFETY RELATED This calculation has been reviewed by me according to the method (s) checked below.

1. Computer Aided calculations 4

Review to determine that the conputer program (s) has been validated and documented, is suitable to the a X problem being analyzed, and that the calculation contains all necessary information for reconstruction at a. 1 later date. b Review to determine that the input data as specific for program execution is consistent with the design X input, correctly defines the problem for the computer algorithm and is sufficiently accurate to produce results within any nLanerical limitations of the program, Review to verify that the results obtained from the program are correct and within stated assumptions and c X limitations of the program and are consistent with the input. d Review validation doctanentation for tenoorary changes to listed, or developmental, or unique single application programs, to assure that methods used adequately validate the program for the intended application. Review of code input only, since the ccuputer program has sufficient history of use at Sargent & Lmdy in e X similar calculations. 1 fX Review arithmetic necessary to prepare code input data. g other: ? l 5 ~,

2. Hand Prepared Calculationa

~ ^ i ~' 1 aX Detailed review of the original calculation. b Review by an alternate, simplified, or approximate method of calculation. } c Review of a representative sanple of repetitive calculations. d Review of the calculation against a similar calculation previously performed. l 1 ] 3. Revisions a Editorial changes only. b Elimination of unapproved input data without altering calculation results. e other: 4. Other i / / n Reviewer: Date: 3/11/93 bl1LLIAM J JOHNSp .._m ________.____M a. _. _ _ _. _ _.}}

ML20058P640

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