ML060120479

Calculation EC-ENVR-1059, Crhe Accident Dispersion Factors (X/Q) RB U2 Intake.

ML060120479
Person / Time
Site:	Susquehanna
Issue date:	07/19/2005
From:	Waselus M M, Weise K E Susquehanna
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
PLA-5963 EC-ENVR-1059
Download: ML060120479 (36)

Text

NUCLEAR ENGINEERING CALCULATION COVER SHEET 1. Page 1 of 36 NEPM-QA..0221-1 Total Pages 36>2. TYPE: CALC ,3. NUMBER: EC-ENVR-1059

>4. REVISION:*>5. UNIT 3 *>6. QUALITY CLASS:>7. DESCRIPTION:

CRHE Accident Dispersion Factors (X/Q) RB U2 Intake.0 8. SUPERSEDED BY: 9. Alternate Number: 10. Cycle: I1. Computer Code/Model used: ARCON96 12. Discipline:

R>13. Are any results of this calculation described in the Licensing Documents?

s Yes, RefertoNDAP-QA-0730andNDAP-OA-0731 0 No>14. Is this calculation changing any method of evaluation described in the FSAR and using the results to support or change the FSAR? (Refer to PPL Resource Manual for Definition of FSAR)3 Yes, 50.59 screen or evaluation required.

0 No>15. Is this calculation Prepared by an External Organization?

ED Yes 5 No EG771 Qualifications may not be required for Individuals from external organizations (see Section 7.4.3).>16.>17.>18.>19.Prepared by: Reviewed by: Verified by: Approved by: M. M. Waselus AAAA A -. -.L-- ff.-W '. ..-Print Name(EG771 Qualification Required)

Signature te K. E. Weise 1-LZ -o-Print Name(EG771 Qualitication Required) nSigjnature Date K. E. Weise 7h213 Print Name(EG771 Qualification Required)

%f , Date M. G. Caplotis '4, 7/Z/Cr Print Name(Qualified per NEPM-QA-0241 and comply with Section 7.8 of NEPM-OA-0221)

-'VPe eLNr T. KAr Signafure eve o.-Date-7 fqlhA>20. Accepted by:-- .. ----- .-- ----i -i -m -Print Name(EG771 Qualification Required) and comply with Sertion 7.9 of NEPM-OA-0221 Signature 0 Date TO BE COMPLETED BY DCS DCS SIGNATURE/DATE I ADD A NEW COVER PAGE FOR EACH REVISION FORM NEPM-OA-0221-1.

Revision B. Page I of 1, ELECTRONIC FORM' Verified Fields> REQUIRED FIELDS I AD A NE CO E PAG FO EA. RISO Vfe .F _ ___.e _._. s_ADD A NEW COVER PAGE FOR EACH REVISION' Verified Fields I PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. m. Waselus (X/0) RB U2 Intake Sh. No. 2 Checked By K. E. Weise TABLE OF CONTENTS SECTION Page 1.0 PURPOSE 3

2.0 CONCLUSION

S AND RECOMMENDATIONS 4 3.0 ASSUMPTIONS

/ INPUT 5 4.0 METHODOLOGY 5 5.0 RESULTS I1

6.0 REFERENCES

12 Attachment 1 -RB2TBIEV.log 14 Attachment 2 -RB2TB2EV.Iog 18 Attachment 3 -RB2SGTSV.log 22 Attachment 4 -RB2MSTP.log 26 Attachment 5 -RB2TBMST.log 30 Attachment 6-Building Cross Sectional Area 34 PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/1 l/05 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. M. Waselus (W/M) RB U2 Intake Sh. No. 3 Checked By K. E. Weise 1.0 PURPOSE The purpose of this analysis is to calculate short term accident yjQ's for the SSES Control Room Habitability Envelope (CRHE) using the methodology provided in NUREG/CR-6331

-ARCON96 (Reference

1) and onsite meteorological data documented in Reference

2. The ARCON96 code uses hourly meteorological data and recently developed methods for estimating yjQ's in the vicinity of buildings to calculate relative concentrations at control room air intakes that would be exceeded no more than five percent of the time. These concentrations are calculated for averaging periods ranging from one hour to 30 days in duration.

The term ,IQ (sec/rn 3) is an expression of the relative dispersion occurring between a source (release) location and a receptor location.

This relative dispersion is used to determine the expected atmospheric concentration at some defined distance away from the source for a known quantity of effluent released.The potential release points evaluated in this analysis are defined as follows: 1. Reactor Building Unit 1 exhaust vent.2. Reactor Building Unit 2 exhaust vent.3. Turbine Building Unit 1 exhaust vent.4. Turbine Building Unit 2 exhaust vent.5. Standby Gas Treatment System exhaust vent.6. Reactor Building Unit 1 closest distance.7. Reactor Building Unit 2 closest distance.8. Turbine Building Unit 1 closest distance.9. Turbine Building Unit 2 closest distance.10. Reactor Building Unit 1 main steam tunnel blowout panel.1 1. Reactor Building Unit 2 main steam tunnel blowout panel.12. Turbine Building Unit I main steam tunnel blowout panel.13.Turbine Building Unit 2 main steam tunnel blowout panel.13.Turbine Building Unit 2 main steam tunnel blowout panel.

PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Caic. No. EC-ENVR-1059 Designed By M. M. Waselus (X/O) RB U2 Intake Sh. No. 4 Checked By K. E. Weise The CRHE outside air intake is located on the roof of the Unit 2 reactor building in the vicinity of column lines U and 36.References 7 to 23 provide details of the layout of the SSES plant structures, exhaust vents and components.

By inspection of the locations of the potential release points relative to the location of the CRHE intake and the potential to be a source of post LOCA activity release, release points 3, 4, 5, 11 and 13 (listed below) are seen as limiting and are further evaluated in detail herein. The Reactor Building exhaust vents (release points 1 & 2) are not a source of post LOCA activity releases.

The Reactor Building closest distance (release points 6 & 7) would only be potential release points during the 10 minute drawdown period. During this time there is negligible activity released to the Reactor Building available for release to the environment.

The Turbine Building closest points (release points 8 & 9) are bounded by the Turbine Building exhaust vents (release points 3& 4) which are at the same elevation as the CRHE Intake. The Reactor Building and Turbine Building Unit 1 blowout panels (release points 10 & 12) are bounded by the Reactor Building and Turbine Building Unit 2 blowout panels (release points 11 & 13). See Figure 1 on page 10 for the relative locations of the 13 release points and the CRHE outside air intake. The specific locations requiring ARCON96 yx 1 s are: 3. Turbine Building Unit 1 exhaust vent.4. Turbine Building Unit 2 exhaust vent.5. Standby Gas Treatment System exhaust vent.I 1. Reactor Building Unit 2 main steam tunnel blowout panel.13. Turbine Building Unit 2 main steam tunnel blowout panel.

2.0 CONCLUSION

S AND RECOMMENDATIONS The CRHE yjQ's for the above release points as determined in this calculation are listed as follows.

PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Caic. No. EC-ENVR-1059 Designed By M. hi. Waselus v/OQ) RB U2 Intake Sh. No. 5 Checked By K. E. Weise# Release Point CRHE /0'S (sec/m 3) without Occupancy Correction Factors_ Time Period 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> X to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 to 4 days 4 to 30 days TB Unit I Exhaust Vent 1 .24E-03 9.55E-04 3.14E-04 1 .99E-04 1.73E-04 4 TB Unit 2 Exhaust Vent 1.36E-03 1.03E-03 3.36E-04 2.20E-04 1.85E-04 5 SGTS Exhaust Vent 1.45E-03 1.12E-03 3.55E-04 2.29E-04 2.01E04 11 RB Unit 2 MST Blowout Panel 1.94E-03 1.41 E-03 5.12E-04 3.28E-04 2.68E04 13rB Unit 2 MST Blowout Panel I 1 .47E-03 1.01 E-03 4.01 E-04 2.95E-04 2.26E-04 These X/gQ values are to be used in subsequent CRHE radiological evaluations for SSES.3.0 ASSUMPTIONS I INPUT There are no assumptions in this analysis which require future confirmation.

The input data and assumptions used in this analysis are summarized as follows: 1. Reactor building grade elevation

-670' (Reference 9).2. Turbine and Control building grade elevation

-676' (Reference 9).3. Elevation of the 5 release points and references are shown on Table 2.4. All release points are assumed to be ground level release type as discussed in References 4 and 6.5. Plant north and true north are essentially the same at SSES.6. Other input Is referenced as appropriate throughout the analysis.4.0 METHODOLOGY The X/Q's for the SSES CRHE are determined using the ARCON96 computer code.ARCON96 mainly requires inputs involving physical relationships between release points and receptor locations.

Table 1 lists the required inputs in order for ARCON96 to provide the z 0 Q's. ARCON96 also has default values for other parameters used in the dispersion model, but they are not normally changed. These parameters, as used herein, will remain the default values except for the Surface Roughness Length and herein, will remain the default values except for the Surface Roughness Length and PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Caic. No. EC-ENVR-1 059 Designed By M. M. Waselus (CQ)j RB U2 Intake Sh. No. 6 Checked By K. E. Weise Averaging Sector Width Constant, which will be set at 0.2 and 4.3, respectively, in lieu of the default values of 0.1 and 4.0, in accordance with the recommendations in USNRC Regulatory Guide 1. 194 (Reference 3).Table 1 -Inputs ruired for ARCON96 Meteorological Input Receptor Input Number of Met Data Files Distance to receptor Lower Measurement Height Intake Height Upper Measurement Height Elevation Difference

_Wind Speed Direction to Source Source Input Release Type Output Files Release Height Output File Name fn.log Building Area CFD File Name fn.cfd Vertical Velocity Expanded Output no Stack Flow Stack Radius Meteorological Input The meteorological data files consist of five files documented in Reference

2. The meteorological data consists of five years of hourly data, covering the years from 1999 to 2003. Each record of the hourly data contains a location identifier, Julian day (1-366), hour (0 to 23), low-level direction, low-level speed, stability class (1 =A to 7=G), upper level direction, and upper level speed. The identifier and upper level data Is optional.Wind speeds are entered in tenths of a reporting unit with no decimal. Wind directions are from 1 to 360 in degrees.These five files were combined into one file for ease of code execution.

This file contains all the data for the SSES site from 1999-2003, which satisfies the ARCON96 (Reference

1) requirements for having 3 to 5 years of hourly data. The Upper and Lower¶easurement Heights are 1Oim and 60 m, respectively, and the Wind Speed units are mn/s (Reference 2).

PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Calc. No. EC-ENVR- 1059 Designed By M. M. Waselus (YXQ) RB U2 Intake Sh. No. 7 Checked By K. E. Weise Source Input Five Source (or Release) points are analyzed.

These sources are chosen to primarily support Condition IV type accidents, but are not limited to just these accidents.

The release points along with the release height and references are listed in Table. 2.Table 2- Release Points and Release Heights# Description Release Release Release Reference Elevation, ft Height, ft (1) Height, m 3 Turbine Building Unit 1 exhaust vent 874.7 204.7 : 62.4 16 4 Turbine Building Unit 2 exhaust vent 874.7 204.7 62.4 16 5 Standby Gas Treatment System exhaust vent 874.7 204.7 62.4 16 11 RB Unit 2 main steam tunnel blowout panel 802.5 132.5 40.4 18.13 TB Untt 2 main steam tunnel blowout panel 717.5_ 47.5 14.5 19,21 1. Release height = Release elevation (ft) -670 ft (grade elevation for RB).The Building Area used for determining the wake effects is 2685 m 2 per Reference 5 (included as Attachment 6).The remaining values for Source input (vertical velocity, stack flow and stack radius)are specified as 0 since only ground level release types are being analyzed.Receptor Input The receptor considered in the calculation is the SSES CRHE outside air intake. The CRHE Intake is approximately located at column lines U and 36 on the roof of the Unit#2 Reactor Building.

Reference 12 provides a sketch of the general arrangement of several of the release points. No dimensions are taken from Reference 12, it is used for general orientation only. The CRHE intake elevation is taken as the Reactor Building roof elevation of 872' (Reference 1). Grade elevation for the SSES site at the Reactor Building is 670' (Reference 9). Therefore, the CRHE intake height is 202' [872' -670']Building is 670' (Reference 9). Therefore, the CRHE intake height is 202' 872 -b(j(j PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CR~HE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. M. Waselus (v/O) RB U2 Intake Sh. No. 8 Checked By K. E. Weise or 61.6 m. The Turbine Building elevations are measured from the Turbine Building grade elevation of 676' (Reference

9) and the elevation difference is +6 feet or +1.8 m.This only affects release point 13, TB Unit 2 main steam blowout panel.For release points 3, 4 and 5 the release height is conservatively set equal to the intake height at a value of 0. (No credit is taken for any elevation difference).

With the combinations of release points and intake identified, the direction and distance between the release point and the intake is determined by scaling from the reference drawings.

Wind direction data are recorded as the direction from which the wind blows (e.g., a north wind blows from the north, a wind blowing out of the west is recorded with a direction of 270 degrees).

The direction input to ARCON96 is the wind direction that would carry the plume from the release point to the intake. For example, an analyst standing at the intake facing west to the release point, would enter 270 degrees; an analyst facing north, would enter 360 degrees, etc.The source-to-receptor distance is the shortest horizontal distance between the release point and the intake. ARCON96 uses this distance and the elevations of the source and receptor to calculate the slant path. For releases within building complexes, the distance between the release point and the intake could be through intervening buildings.

In these cases, the length of the shortest path is taken around or over the intervening building as the source-to-receptor distance (e.g., utaut string length").

Taut string distances are not used in this analysis and the horizontal values from Table 3 are conservatively used directly in ARCON96. The source-to-receptor horizontal distances and direction are listed in Table 3. The values were determined by scaling from the reference drawings.

PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. M. Waselus (X/O) RB U2 Intake Sh. No. 9 Checked By K. E. Weise Table 3 -Release Point Horizontal Distances and Directions

1. Description Horizontal Distance Direction Reference meters degrees 3 TB Unit 1 exhaust vent 66.1 322 11,16,22 4 TB Unit 2 exhaust vent 62.6 317 11,16,22 5 SGTS exhaust vent 60.98 320 11,16,22 11 RB Unit 2 MST blowout panel 47.26 299 11,17,23 13 TB Unit 2 MST blowout panel 40.85 255 19,21 The approximate roof elevations for the structures are listed as follows: 1. Turbine Building 786' Reference 9 2. Control Building 810' Reference 9 3. Reactor Building 872' Reference 11 PP&L CALCULATION SHEET Dept. 0341 Rad &Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Caic.No. EC-ENVR-1059 Designed By M. M. Waselus (X/O) RB U2 Intake Sh. No. 10 Checked By K. E. Weise The overall site/building arrangement is shown on Reference

10. The relative locations of the release points corresponding to the above are shown as follows on Figure 1: FIGURE 1 North TB U2 TBUl.11 CRHE 10 4 3 9 13-CRHE Outside Air Intake 5 7 6 RB U2 RB UI.2 1 8 12 PP&L CALCULATION SHEET Dept, 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRIJE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. M. Waselus (XM RB U2 Intake Sh. No. I I Checked By K. V. Weise -5.0 5.0 RESULTS The results of the analysis are provided on the ARCON96 computer outputs (Attachments 1 to 5) and summarized on Table 5. As noted in Reference 6, section 4.2.6, ARCON96 output does not include the CRHE occupancy correction factors that may be applied in CRHE dose evaluations.

Table 5'- CRHE X/Q's as a Function of Release Point without Occupancy Correction

_ f 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1 to 4 days 4 to 30 days ARCON96 Reference eas elease Point sec/m 3 sec/M 3 sec/m 3 sec/M 3 sec/M 3 file Unii TB Unit 1 Exhaust Vent 1.24E-03 9.55E-04 3.14E-04 1.99E-04 1.73E-04 RB2TB1EV.log Attachment 1 UnitTB Unit 2 Exhaust Vent 1.36E-03 1.03E-03 3.36E-04 2.20E-04 1.85E-04 RB2TB2EV.log Attachment 2 ,TS i SGTS Exhaust Vent 1 .45E-03 1.1 2E-03 3.55E-04 2.29E-04 2.01 E04 RB2SGTSV.log Attachment 3 lUnl 1 RB Unit 2 MST Blowout Panel 1 .94E-03 1.41 E-03 5.12E-04 3.28E-04 2.68E-04 RB2MSTP.log Attachment 4 lUni 3 TB Unit 2 MST Blowout Panel 1 .47E-03 1.01 E-03 4.01 E-04 2.95E-04 2.26E-04 RB2TBMST.log Attachment 5

PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. M. Waselus (XQ).RB U2 Intake Sh. No. 12 Checked By K. E. Weise

6.0 REFERENCES

1. NUREGJCR-6331, Atmospheric Relative Concentrations in Building Wakes, Revision 1, May, 1997 (ARCON96 computer code).2. EC-ENVR-1057, Offsite xlQ values for SSES Based on 1999 -2003 Meteorological Data, Revision 0.3. USNRC Regulatory Guide 1.194, Atmospheric Relative Concentrations for Control Room Radiological Habitability Assessments at Nuclear Power Plants, June, 2003.4. NEI-99-03, Control Room Habitability Assessment Guidance, Nuclear Energy Institute, 6/2001.5. Building Cross Sectional Area calculated herein included as Attachment

6.6. USNRC

Regulatory Guide 1.183, Altemative Radiological Source Terms For Evaluating Design Basis Accidents At Nuclear Power Reactors, July 2000.7. PPL Drawing E-106446 Sheet 10 Revision 16.8. PPL Drawing E-106446 Sheet 15 Revision 9.9. PPL Drawing E-106312 Revision F.10. PPL Drawing E105002 Sheet 1 Revision 12.11. PPL Drawing E-1 05004 Sheet 7 Revision 27.12. FSAR Figure 6.4-2. Revision 49.13. PPL Drawing E-105004 Sheet 4 Revision 25.14. PPL Drawing E-106454 Sheet 14 Revision 11.15.PPL Drawing E-106458 Sheet 14 Revision 8.16. PPL Drawing E-t 06429-8 Revision 16.17. PPL Drawing E-1 05007 Sheet 1 Revision 9.18. PPL Drawing E-1 05618 Revision 1.19. PPL Drawing E-105670 Revision 8.20. PPL Drawing E-105005 Sheet 1 Revision 9.21. PPL Drawing E-105004 Sheet 3 Revision 26.22. PPL Drawing E-106429-10 Revision 15.23. PPL Drawing E-1 05004 Sheet 6 Revision 22.Z1. i-'L urawing t-1U UU4 bneet j Kevision zo.

PP&L CALCULATION SHEET Dept. 0341 Rad & Eff Tech. PROJECT Date 7/11/05 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1059 Designed By M. M. Waselus fzX)QRB U2 Intake Sh. No. 13 Checked By K. E. Weise 24. PPL Drawing E-1 05329 Revision 9.25. PPL Drawing E-1 05257 Revision 9.26. PPL Drawing E-1 05259 Revision 8.27. PPL Drawing E-105004 Sheet 5 Revision 27.

Ek-IC-ENVR-1059 Attachmcnt I Page 14 Attachment I -RB2TBlEV.Iog ARCON96 Output for Turbine Building Unit 1 Exhaust Vent ER- I C-ENVR- 1059 Attachment I Page 15 RB2TBIEV.Iog PTitrogram Title: ARCON96.Dd Seveloped For;C late-U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.Xac"RC Contacts: J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jylltnrc.gov Phone: (301) 415 3167 e-mail: jjhanrc.gov Phone: (301) 415 1232 e-mail: lab2(nrc gov C'elcode Developer; J. V. Ramsdell Phone; (509) 372 6316 e-mail: jraasdelllpnl.gov Oumelode Documentation:

NUnEG/CR-6331 Rev. 1 trayhe program was prepared for an agency of the United States Government.

Neither ted:he United States Government nor any agency thereof, nor any of their as, umployees, makes any warranty, expressed or implied, or assumes any legal ty Liability or responsibilities for any third party's use, or the results of such ranyse, of any portion of this program or represents that its use by such third puloarty would not infringe privately owned rights.IRurrogram Run 7/ 9/2005 at .08:47:05 t Af***1***

ARCON INPUT *******efr Number of Meteorological Data Files -Rorc Meteorological Data File Names:\AF C:\ARCO196\SQg9 0-l.MET;ht Height of lower wind instrument

{m) -jht Height of upper wind instrument (m) -I tI Wind speeds entered as miles per hour 1 10.0 60.0 snd-Ldir Luer: ox: ox Ground-level release Release height (m)Building Area (mA2)Effluent vertical velocity (m/e)Vent or stack flow (m43/s)Vent or stack radius Cm)a .0-2685.0 X .00_ .00 w .00 actj Direction

.. intake to source (deg) =322 Ee--IC-ENVR-1059 Attachment I Pagc 16 I di I di:anc kke-ain Wind direction sector width (dog)Wind direction window (deg)Distance to intake (i)Intake height (m)Terrain elevation difference (m)M 90-277 -007-66.1= .0.0 out Output file names 12TB RB2TB1EV.log 12TH RB2TBIEV.cfd.muM Minimum Wind Speed (m/s)'ace Surface roughness length (m):or Sector averaging constant.5.20 4.3;ial Initial value of sigma y:ial Initial value of sigma z= .00 c .00 Lnde Expanded output for code testing not selected Ll.5.5 1a.s n c d e 0 d Total Hours Hours Hours Hours Hours number of hours of data processed a 43824 of missing data -297 direction in window -6049 elevated plume wi dir. in window a 0 of calm winds = 454 direction not in window or calm -37024'RIB DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL PR t LI I LI RAN RAN RAN ZE.X/I ZE AVER. PER.UPPER LIM.LOW LIM, ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qz% NON ZERO I 1.00E-02 1.00E-06 0.6503.0.37024.43527.14.94 2 1.OOE-02 1.00-06 0.8237.0.35244.43481.18.94 4 1.00Z-02 1.00Z-06 0.10974.0.32428.43402.25.28 a 1.001-02 1.OOE-06 0.15307.0.27949.43256.35.39 12 1.001-02 1.00E-06 0.18889.0.24411.43300.43.62 24 1.00E-02 1.00E-06 0.26551.0.16602.43153.61,53 96 1. 00-02 1.00E-06 0.40991.0.1966.42957.95.42 168 1.001-02 1.00E-06 0.42163.0.45e.42621.98.93 360 1.00E-02 1.001-06 0.42457.0.0.42457.100.00 720 1.00E-02 1.00E-06 0.43155.0.0.43155.100.00 I PE 95th PERCENTILE X/Q VALUES 1.24E-03 1.21E-03 1.14R-03 1.03E-03 8.211-04 5.51E-04 2.87E-04 2.441-04 2.09E-04 1.89E-04 X/Q 95% X/Q for standard averaging intervals>2 8 24 4 30 0 2 8 1 4 to to to to to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 8 hours 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4 days 30 days 1.243-03 9. 55B-04 3.14E-04 1.99E-04 1.73E-04 ER-IC-ENVR-1059 Attachment I Page 17 HOURLY VALVE RANGE MAX X/S 1.64E-03 9,54E-04 CE CENTERLINE SE SECTOR-AVERAGE FROCORMAL PROGRAM COMPLETION MIN X/Q 2.512-04 1.46E-04 E(R- I-ENVR-1059 Attachment 2 Page 18 Attachment 2 -RB2TB2EV.Iog ARCON96 Output for Turbine Building Unit 2 Exhaust Vent ER- I C-EN VR- 1059 Attachmncnt 2 Page 19 RB2TB2EV.Iog ITitrogram Title: ARCON96.Dd Developed For:: )ate: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.k.actRC Contacts: J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail; jjhGnrc.gov Phone: (301) 415 1232 e-mail: lab2Qnro.gov CEelCode Developer:

J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdell~pnlgov Ou=Code Documentation:

NURG/CR-6331 Rev. 1%raihe program was prepared for an agency of the United States Government.

Neither ted he United States Government nor any agency thereof, nor any of their asmployees, makes any warranty, expressed or implied, or assumes any legal Xy liability or responsibilities for any third party's use, or the results of such iLanyse, of any portion of this program or represents that its use by such third puloarty would not infringe privately owned rights.IRufrogram Run 7/ 9/2005 at 08:47:46 A T****** ARCON INPUT *Der Number of Meteorological Data Files aorc Meteorological Data File Names;\Al C:\ARCON96\BQ990-1 .MET;ht Height of lower wind instrument tm) -7ht Height of upper wind instrument (m) -i s Wind speeds entered as miles per hour 1 10.0 60.0 and-Ldiz Luec t oi L oj Ground-level release Release height tW)Building Area (mA2)Effluent vertical velocity (m/s)Vent or stack flow (MA3/s)Vent or stack radius (i)-,0-2685,0-.00 W .00 a .00 ER-IC-ENVR-1059 Attachment 2 Page 20 ,ctU Direction

.. intake to source (deg) a 317 I di Wind direction sector width (dog) 90 S di Wind direction window (deg) -272 -002 tanc Distance to intake (m)

• 62.6 ske Intake height (m) -.0 rair Terrain elevation difference (m) = .0 put Output file names 32TI RB2TB2EV.

log 32TE R82TB2ZV.cfd imum Minimum Wind Speed (mWs) = .S Face Surface roughness length (a) -.20 tor Sector averaging constant w 4.3 tia3 Initial value of sigma y -.00 tiaj Initial value of sigma z .00 ind4 Zxpanded output for code testing not selected al r Total number of hours of data processed

-43824 ra c Hours of missing data = 297 rc C Hours direction in window -5830 Ca m Hours elevated plume w/ dir. in window -0 ca ( Hours of calm winds N 454 re ( Hours direction not in window or calm m 37243 rRII DISTRIBUTION

SUMMARY

DATA BY AVRRAGING INTERVAL.P AVER. PER. 1 2 4 8 12 24 96 168 360 720 R L: UPPER LIM. 1.00E-02 1.00E-02 1.00Z-02 1.00E-02 1.001-02 1.00Z-02 1.001-02 1.00E-02 1.00E-02 1.00E-02 N L: LOW LIM. 1.00E-06 1.001-06 1.001-06 1.00Z-06 1.00E-06 1.00E-06 1.00E-06 1.001-06 1.00R-06 1.00E-06 RA) AHOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.F IN RANGE 6284. 7988. 10648. 14825. 18317. 25854. 40946. 42128. 42457. 43155.RAI BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.Zl ZERO 37243. 35493. 32754. 28431. 24983. 17299. 2011. 493. 0. 0.L Xi TOTAL X/Qs 43527. 43481. 43402. 43256. 43300. 43153. 42957. 42621. 42457. 43155.N Z1 % NON ZERO 14.44 18.37 24.53 34.27 42.30 59.91 95.32 98.84 100.00 100.00 h i 95th PERCENTILE X/Q VALUES 1.36E-03 1.33E-03 1.25E-03 1,11e-03 8.933-04 5.94E-04 3.13E-04 2.63E-04 2.25E-04 2.021-04 X/l 95% X/Q for standard averaging intervals

-o 2 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.361-03 o 8 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.03E-03 D 2' 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.36E-04 o 4 1 to 4 days 2.20R-04* 3( 4 to 30 days 1.85E-04 E(L-IC-ENVR-1059 Attachment 2 Page 21 ROURLY VALUE RANGE MAX X/Q 1. 82E-03 1.06E-03 CE SE CENTERLINE SECTOR-AVERAGE MIN X/Q 2.78E-04 1. 62E-04 NROGORMAL PROGRAM COMPLETION EZ- I C-ENVR- 1059 Attachlment 3 Page 22 Attachment 3 -RB2SGTSV.log ARCON96 Output for Standby Gas Treatment System Exhaust Vent E(- I C-EN VR- 1059 Attachment 3 Pagc 23 RB2SGTSV.Iog ZTitrogram Title: ARCON96.Od Developed For: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management C hate: June 25, 1997 11:00 a.m.Ract!RC Contacts: J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: 1301) 415 3167 e-mail: j jhenrc.gov Phone: (301) 415 1232 e-mail: lab28nrc.gov 0elcode Developer:

J. V. Ramsdell Phone: (509) 372 6316 e-mail: jrauadellepnl.gav CumCode Documentation:

NUREG/CR-6331 Rev. 1 tranhe program was prepared for an agency of the United States Government.

Neither ted he United States Government nor any agency thereof, nor any of their es, employees, makes any warranty, expressed or implied, or assumes any legal ly Liability or responsibilities for any third party's use, or the results of such uanyse, of any portion of this program or represents that its use by such third pul6arty would not infringe privately owned rights.lRuwrogram Run 7/ 9/2005 at 06:43:20 A AF*******

ARCON INPUT Mer Number of Meteorological Data Files =Porc Meteorological Data File Names\AF C:\ARCON96\SQ99 01.MET;ht Height-of lower wind instrument (m) -Jht Height of upper wind instrument (m)I or Wind speeds entered as miles per hour 1 10.0 60.0 ind-paws Ldir g. oz t ox Ground-level release Release height (m)Building Area (in2)Xffluent vertical velocity Wmis)Vent or stack flow (=43/s)Vent or stack radius (m)-.0-2685.0.00-.00 a .00 Ea- I C-EN VR- 1059 Attachment 3 Page 24 Icti Direction

.. intake to source (deg) -320 I di Wind direction sector width (dog) a 90 I di Wind direction window (dog) -275 -005:anc Distance to intake (a) -61.0 tke Intake height (m) _ .0-ain Terrain elevation difference (m) = .0 out Output file names 12ag RB2sgtsv.log 12s9 RB2agtsv.cfd mum Minimum Wind Speed (m/). .5.!ace Surface roughness length (m) = .20:or Sector averaging constant 4.3:ial Initial value of sigma y -.00:ial. Initial value of sigma z .00 tnde Expanded output for code testing not selected il n Total number of hours of data processed a 43824 a o Hours of missing data a 297.s d Hours direction in window a 5965 9s e Hours elevated plume wI dir. in window n 0 s o Hours of calm winds a 454-a d Hours direction not in window or calm 37108'RIB DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL PE AVER. PER. 1 2 4 8 12 24 96 168 360 720 LI UPPER LIM. 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.003-02 1.00Z-02 1.00E-02 LI LOW LIM. 1.00E-06 1.00E-06 1.00S-06 1.003-06 1.00E-06 1.00E-06 1.00E-06 1.003-06 1.003-06 1.003-06 RAN ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.RAN IN RANGE 6419. 8132. 10828. 15071. 18596. 26160. 40812. 42116. 42457. 43155.RAN BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. °.Zs ZERO 37108. 35349. 32574. 28185. 24704. 16993. 2145. 505. 0. 0., X/ TOTAL X/Qs 43527. 43481. 43402. 43256. 43300. 43153. 42957. 42621. 42457. 43155.I ZX % NON ZERO 14.75 18.70 24.95 34.84 42.95 60.62 95.01 98.82 100.00 100.00 FP 95th PERCENTILE X/Q VALUES 1.45E-03 1.40E-03 1.33E-03 1.20E-03 9.51z-04 6.37E-04 3.318-04 2.81E-04 2.42E-04 2.19E-04 X/Q 95% X/Q for standard averaging intervals 2 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.45E-03* 8 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.12E-03* 24 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 3.553-04* 4 1 to 4 days 2.29E-04.30 4 to 30 days 2.01E-04 ER-IC-ENVR-1059 Attachment 3 Page 25 HOURLY VALUE RANGE MAX X/Q 1.91E-03 1.11E-03 CE SE CENTERLINE SECTOR-AVERAGE MIN X/Q 2. 92E-04 1. 70E-04 FROQORMAL PROGRAM COMPLETION ER- IC-ENVR- 1059 Attachment 4 Page 26 Attachment 4 -RB2MSTP.log ARCON96 Output for Reactor Building Unit 2 Main Steam Tunnel Blowout Panel ER-I C-EN VR-1059 Attachment 4 Page 27 RB2MSTP.log lTifrogram Title: ARCON96.Od Developed For: r )ate: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.tacNRC Contacts: J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhenrc.qov Phone: (301) 415 1232 a-mail: lab2enre.gov

('eldode Developer; J. V. Ramsdell Phone: (509) 372 6316 e-mail: j ramsdelltpnl.gov CnumCode Documentation:

NUREG/CR-6331 Rev. 1 4rafhe program was prepared for an agency of the United States Government.

Neither ted he United States Government nor any agency thereof, nor any of their es,imployees, makes any warranty, expressed or implied, or assumes any legal ty Liability or responsibilities for any third party's use, or the results of such Lanyae, of any portion of this program or represents that its use by such third puloarty would not infringe privately owned rights.IRuxlrogram Run 7/ 9/2005 at 10:34:08 I******* ARCON INPUT Z 3er Number of Meteorological Data Files -morc Meteorological Data File Names: \SF C:\ARCON96\SQ99 0.I.XET -;ht Height of lower wind instrument (m} -7ht Height of upper wind instrument (im)I ar Wind speeds entered as miles per hour 1 10.0 60.0 ind-last Ldir Luer: o: ox Ground-level release Release height (m)Building Area (mA2)Effluent vertical velocity (m/a)Vent or stack flow (mA3/s)Vent or stack radius (m)-40.4 W 2685.0 I .00 e .00 W .00 ER- I C-ENVR- 1059 Attachment 4 Pagc 28 Icti Direction

.. intake to source (dog) -299 I di wind direction sector width (dog) a 90 I di Wind direction window (dog) -254 -344:anc Distance to intake Cm) = 47.3 tke intake height (m) 61.6.air Terrain elevation difference ) w .Yut output file names 12MS RB2MSTP.log a2M6S RB2MSTP.cfd uLEua Minimum Wind Speed (mWs) =5'ace Surface roughness length (m) -.20.or Sector averaging constant -4.3:ial initial value of sigma y -.00:ial Initial value of sigma z -.00 inds expanded output for code testing not seleoted ml r Total number of hours of data processed a 43824 Is C Hours of missing data -297:0 c Hours direction in window = 6493 e Hours elevated plume w/ dir, in window -0 Is c Hours of calm winds = 668 Zse Hours direction not in window or calm a 36366 LRIE DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL I PI AVER. PER. 1 2 4 9 12 24 96 168 360 720 t L3 UPPER LIM. 1.00 .OOE-02 1.00E-02 l.00E-02 1,OOE-02 1.006-02 1.00Z-02 1.00Z-02 l.00E-02 1.001-02 l.OOE-02 f L3 LOW LIM. 1.OOE-06 1.001-06 1.00E-06 1.O-06 1.OOE-06 1.005-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 RAX ABOVE RPANG 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.RAB IN RANGE 7161. 9051. 11968. 16489. 20083. 27657. 41411. 42301. 42457. 43155.RAb BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.ZE ZERO 36366. 34430. 31434. 26767. 23217. 15496. 1546. 320. 0. 0..X/ TOTAL X/Qs 43527. 43481. 43402. 43256. 43300. 43153. 42957. 42621. 42457. 43155.q ZE % NON ZERO 16.45 20.82 27.57 38.12 46.38 64.09 96.40 99.25 100.00 100.00 1 PE 95th PERCENTILE X/Q VALUES 1.945-03 1.86E-03 1.71E-03 1.55E-03 1.26Z-03 8.57E-04 4.60E-04 3.85E-04 3.28E-04 2.941-04 X/C 95% X/Q for standard averaging intervals Z 2 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.94R-03 a 8 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.41Z-03; 24 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5.12E-04 i 4 1 to 4 days 3.28Z-04 z 3C 4 to 30 days 2.68Z-04 E(- I C-ENVR- 1059 CE CENTERLINS SR SECTOR-AVERAGE NROGORMAL PROGRAM COMPLETION Attachmcnt 4 Puage 29 HOURLY VALUE RANGE MAX X/Q 2.89E-03 1. 68E-03 MIN X/Q 2. 36E-04 1. 36E-04 Ea- IC-IENVR-1059 Attachment 5 Page 30 Attachment 5 -RB2TBMST.log ARCON96 Output for Turbine Building Unit 2 Main Steam Tunnel Blowout Panel ER- I C-ENVR- 1059 Attachment 5 Page 31 RB2TBMST..og PTitrogram Title: ARCON96.Dd Peveloped For: r late: U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.kactfRC Contacts: J. Y. Lee J. J. Hayes L. A Brown Phone: (301) 415 1080 e-mail: jyllenrc.gov Phone: (301) 415 3167 e-mail: jjhenrogov Phone; (301) 415 1232 e-mail: lab2@nrc.gov Qeldode Developer:

J. V. Ramadell Phone: (509) 372 6316 e-mail: jramsdellapnl.gov eumznode Documentation:

NUREG/CR-6331 Rev. 1 2ra&Xhe program was prepared for an agency of the United States Government.

Neither ted he United States Government nor any agency thereof, nor any of their as,imployeas, makes any warranty, expressed or implied, or assumes any legal ly viability or responsibilities for any third party's use, or the results of such tanytse, of any portion of this program or represents that its use by such third puloarty would not infringe privately owned rights.ERurrogram Run 7/ 9/2005 at 10:39;56 A$*******

ARCON INPUT ********)or Number of meteorological Data Files -iorc Meteorological Data File Names:\AF CAARCON96\SQ99_0-1.MET

ht Height of lower wind instrument (i) -jht Height of upper wind instrument (m) -J s; Wind speeds entered an miles per hour 1 10.0 60.0 ind-base Ldir Luer

ox t 03 Ground-level release Release height (m)Building Area (mA2)Effluent vertical velocity (m/s)Vent or stack flow mA^3/s)Vent or stack radius (m)= 14.5-2685.0* .00-.00.00 ER- I C-ENVR- 1059 Attachment 5 Pagc 32 poti Direction

.. intake to source (deg)

• 255 I di Wind direction sector width (deg) -90 I di Wind direction window (dog) -210 -300 Anc Distance to intake (m) = 40.8 tke Intake height (i) 61.6 ,ain Terrain elevation difference (m) -1.8 out Output file names 12TB RB2TBMST.log 12TB RB2TBMST.cfd.muM Minimum Wind Speed (m/a) = .5'ace Surface roughness length (m) -.20:or Sector averaging constant = 4.3:ial Initial value of sigma y -.00:ial Initial value of sigma z -.00 tnde Expanded output for code testing not selected 11 n Total number of hours of data processed a 43824.s c Hours of missing data , 297.s d Hours direction in window -9752 Hs e ours elevated plume w/ dir. in window -0 s c Hours of calm winds n 454 rs d Hours direction not in window or calm ^ 33321 ,RIB DISTRIBUTION SUMMART DATA BY AVERAGING INTERVAL PR AVER. PER. 1 2 4 8 12 24 96 168 360 720 t LI UPPER L1h. l.OOE-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00E-02 1.00Z-02 1.OOE-02 1.00Z-02 T LI LOW LIM. 1.00X-06 1.00E-06 1.001-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 1.00E-06 RAN ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.RAN IN RANGE 10206. 12801. 16612. 22124. 26303. 33407. 42414. 42583. 42457. 43155.PM^ BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.ZE ZERO 33321. 30680. 26790. 21132. 16997. 9746. 543. 38. 0. 0..X TOTAL X/Qs 43527. 43481. 43402. 43256. 43300. 43153. 42957. 42621. 42457. 43155.1 ZE % NON ZERO 23.45 29.44 38.27 51.15 60.75 77.42 98.74 99.91 100.00 100.00 a PR 95th PERCENTILE X/Q VALUES 1.47E-03 1.40E-03 1.27E-03 1.13E-03 9.071-04 6.43E-04 3.82E-04 3.243-04 2.871-04 2.47E-04 X/C 95% X/Q for standard averaging intervals) 2 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.471-03) 8 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.01R-03) 24 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 4.01E-04) 4 1 to 4 days 2.95E-04 1 3C 4 to 30 days 2.26E-04 EC- I C-ENVR- 1059 Attachment 5 Page 33 HOURLY VALUE RANGE MAX X/Q 2.02E-03 1.18E-03 CE CENTERLIVE SE- SECTOR-AVERAGE NROGORMAL PROGRAM COMPLETION MKN X/Q 2.21E-04 1 .29E-04 EC-ENVR-1059 Attachment 6 Page 34 Attachment 6 -Building Cross Sectional Area Calculation EC-ENVR-1059 Attachment 6 Page 35 Analysis Of Vertical Cross-Sectional Area (Minimum)Of Reactor Building For Evaluation Of XIQ's The general arrangement of the reactor building is shown in SSES design drawing El 06312, Revision F (Reference 9). Above the turbine building roof elevation, the reactor building area includes the superstructure area and the area associated with the blowout panels and duct spaces between Column Lines P and M (see SSES design drawing E105004, Sheet 6, Revision 22;Reference 23). Below the turbine building roof elevation, credit is only taken for the reactor building area between Column Lines U and P. including the concrete outer walls.1. Reactor Building Roof to Bottom Of Superstructure

References:

SSES Drawings E105007, Sheet 1, Revision 9 (Reference 20)E105329, Revision 9 (Reference 24)Reactor Building Roof Elevation

= 873'-1% = 873.12 ft Superstructure Bottom Elevation 809'- 7 5/8" = 809.64 ft Height = 873.12 ft -809.64 ft = 63.49 ft Width Of Superstructure

= 161'-9 5/8' = 161.80 ft Area =63.49 ft X 161.80 ft= 10273 ft 2 2. Reactor Building Bottom Of Superstructure to Turbine Building Roof Elevation

References:

SSES Drawings E105004, Sheet 7, Revision 27 (Reference 11)E105007, Sheet 1, Revision 9 (Reference 20)E105004, Sheet 6, Revision 6 (Reference 22)E105329, Revision 9 (Reference 24)El05257, Revision 9 (Reference 25)El 05259, Revision 8 (Reference 26)E105004, Sheet 5, Revision 27 (Reference 27)Superstructure Bottom Elevation

= 809'- 7 5/8' = 809.64 ft Turbine Building Roof Elevation

= 789'-8Y 4 "= 789.73 ft Height = 809.64 ft -789.73 ft = 19.91 ft Width = (1'-6") + Distance Column U to Column P + (16'-0") + (1'-9 5/16")Width = (1'-6") + (26'-6") + (27'-6") + (17'-6") + (8'-0") + (25'-6') + (29'-O")+(16'-0")

+ (1'-9 5116")Width = 153.28 ft Area = 19.91 ft X 153.28 ft = 3052 ft 2 lAtIA0, -4'= r fND 4 EC-ENVR-1 059 Attachment 6 Page 36 3. Turbine Building Roof Elevation to Grade Elevation

References:

SSES Drawings El 05007, Sheet 1, Revision 9 (Reference 20)El 05257, Revision 9 (Reference 25)E105259, Revision 8 (Reference 26)Turbine Building Roof Elevation

= 789'-BY4 " = 789.73 ft Grade Elevation

= 676'-0" Height = 789.73 ft -676 ft = 113.73 ft Width = (1'-6") + Distance Column U to Column P + (1'-6")Width = (1'-6") + (26'-6") + (27'-6") + (1 7'-6") + (8'-0") + (25'-6") + (29'-0")f(l

'-6")Width = 137 ft Area = 113.73 ft X 137 ft = 15581 ft 2 4. Total Reactor Building Minimum Cross-Sectional Area Total Area = 10273 ft 2 + 3052 ft 2 + 15581 ft 2 Total Area = 28906 ft 2 x (.0929 m 2/ ft 2) = 2685 m 2