ML063310457

Calculation EC-ENVR-1058, Rev 1, Crhe Accident Dispersion Factors (X/Q)

ML063310457
Person / Time
Site:	Susquehanna
Issue date:	11/10/2006
From:	Susquehanna
To:	Office of Nuclear Reactor Regulation
References
EC-ENVR-1058, Rev 01
Download: ML063310457 (37)

Text

Attachment 4 to PLA-6124 EC-ENVR-1058, Revision I

PCAF 42005-1237 Page 4 of5 NUCLEAR ENGINEERING CALCULATION COVER SHEET NEPM-QA-0221-1 Page I of 36 Total Pages 36

@2. TYPE:

CALC

-'3. NUMBER:

EC-ENVR-1058

>'4. REVISION:

i

• p.5. UNIT 3

• "-6. QUALITY CLASS:

Q

• 7. DESCRIPTION:

CRHE Accident Dispersion Factors (x/Q)

8. SUPERSEDED BY:

N/A

9. Alternate Number:

N/A

10. Cycle:

N/A

11. Computer Code/Model used:

ARCON96

12. Discipline:

R

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

. Yes, Re/er to NDAP-QA-0730 and NDAP-QA-0731 El 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)

[

Yes, 50.59 screen or evaluation required.

F] No

> 15. Is this calculation Prepared by an External Organization'?

[

Yes DNo EG771 Qualifications may not be required for individuals from external organizations (see Section 7.4.3).

> 16. Prepared by:

M. M. Waselus J

_J a..A.A.--.

Iaa/po/0 b

Print Name (EG771 Qualification Required) nature Date

-17. Reviewed by:

R. E. Anderson

/

Pr'int Name (EG771 Qualification Required)

Si-ature batS

,- 18. Verified by:

R. E. Anderson I*'L*y.,*l' (1/io/o(o Prinit Name (EG771& QADR Qualification Required)

Signature IDat*

-19.

Approved by:

P. L. Bunker

-/II0 Print Name (Qualified per NEPM-QA-0241 and compiv w ith Section Signature Date 7.8 of NEPM-OA-t022!1)

20. Accepted by:

\\Thr /

Print Name (EG771 Qualification Required) and coanmpi with Signature -se Date Section 7.9 of NEPM-QA-0221 ADD A NEW COVER PAGE FOR EACH REVISION FORM NEPM-QA-0221-1, Revision 9, Page I of I, ELECTRONIC FORM

• Verified Fields

> REQUIRED FIELDS

Page 2 CALCULATION REVISION DESCRIPTION SHEET NEPM-QA-0221-2 REVISION NO:

I CALCULATION NUMBER:

EC-ENVR-1058

[]

FULL REVISION I-SUPERSEDED D]

PAGE FOR PAGE LI]

VOIDED Revised A

R R

Description Pages d

p m

of Revision on the Listed Pages d

I v

All Total revision

[

D

_-1

[__

El F]

71:

__ DF-1 El F-1 El]

E-3 i-1

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El D--D FORM NEPM-QA-0221-2, Revision 5, Page I of I ELECTRONIC FORM

Page 3 TECHNICAL CHANGE

SUMMARY

PAGE NEPM-QA-0221-5 Calculation Number:

EC-ENVR-1058 Revision No. I This form shall be used to (1) record the Technical Scope of the revision and (2) record the scope of verification if the calculation was verified. It should not be more than one page. Its purpose is to provide summary information to the reviewer, verifier, approver, and acceptor about the technical purpose of the change. For non-technical revisions, state the purpose or reason for the revision.

Scope of Revision: Revision 1 is a total revision to the calculation. Revision 1 corrects the units of the wind speeds input to the ARCON96 code from meters/second to mph.

Scope of Verification (If verification applies): Verify design input, assumptions, methodology, arithmetic, computer code input/output, results and conclusions.

NEPM-QA-0221-5, Revision 0 Page 1 of I ELECTRONIC FORM

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus

-XLQ)

Sh. No.

4 Checked By R.E. Anderson TABLE OF CONTENTS 1.0 PURPOSE 5

2.0 CONCLUSION

S AND RECOMMENDATIONS 6

3.0 A S SU M PT IO N S / IN PU T..................................................................

6 4.0 METHODOLOGY 7..........

7 5.0 RESULTS 14 6.0 R E F E R E N C E S........................................................................................................................................

15 - EXCEL File - Taut String Distances 16 - EXCEL File (Formula)- Taut String Distances......................................................................

18 - TB I EVZZ.Iog........................................................

20 - TB2EVZZ.Iog 23 A ttachm ent 5 - SG T SEV ZZ.log.....................................................

26 - PLE-23733 - Cross Sectional Area.........................................

29 - TB2ZZAZ.Iog 34

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus Q

Sh. No.

5 Checked By R.E. Anderson 1.0 PURPOSE.

The purpose of this analysis is to calculate short term accident Y/Q'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 z/Q values determined herein are only used to estimate the potential dose consequences from the external cloud surrounding the CRHE and are not used to model infiltration into the CRHE via the CRHE outside air intake. The ARCON96 code uses hourly meteorological data and recently developed methods for estimating y/Q's in the vicinity of buildings to calculate relative concentrations at receptor locations 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 yjQ (sec/m 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.

11. 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

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Caic. No. EC-ENVR-1058 Designed By M. M. Waselus

/_(Q)

Sh. No.

6 Checked By R.E. Anderson 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 walls and the potential to be a source of post LOCA activity release, release points 3, 4 and 5 (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, from low pressure turbine, elevation 729') are bounded by the Turbine Building exhaust vents (release points 3 & 4) which are overall closer to the CRHE walls. The Reactor Building and Turbine Building. Unit 1 blowout panels (release points 10 & 12) and the Reactor Building and Turbine Building Unit 2 blowout panels (release points 11 & 13) are not required to be evaluated herein since they only pertain to the Main Steam Line Break and are evaluated in EC-RADN-1 128 (Reference 24). See Figure 1 on page 11 for the relative locations of the 13 release points and the CRHE outside air intake. The specific locations requiring ARCON96 7/Qs for use in the applicable radiological evaluations are:

3. Turbine Building Unit 1 exhaust vent.

4. Turbine Building Unit 2 exhaust vent.

5. Standby Gas Treatment System exhaust vent.

2.0 CONCLUSION

S AND RECOMMENDATIONS The CRHE 1/Q's for the pertinent release points as determined in this calculation are listed as follows.

1. Release Point CRHE x/Q'S (sec/m 3) without Occupancy Correction Factors

]Time Period 0to2 hours 2to8 hours 8to24hours 1 to4days 4to30days 3 TB Unit 1 Exhaust Vent 4.03E-03 3.61E-03 1.56E-03 1.12E-03 8.71E-04 4 TB Unit 2 Exhaust Vent 4.72E-03.

4.25E-03 1.84E-03 1.32E-03 1.03E-03 5 JSGTS Exhaust Vent 4.15E-03 3.61E-03 1.57E-03 1.12E-03 8.86E-04 3.0 ASSUMPTIONS / 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. Control building grade elevation - 676' (Reference 9).

3. Elevation of the 3 release points and references are shown on Table 2.

PP&L CALCULATION SHEET Dept.

0341 Rad & EffTech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus (EQ.)

Sh. No.

7 Checked By R.E. Anderson

4. All release heights are taken from the 676' grade elevation.

5. All release points are assumed to be ground level release type as discussed in References 4 and 6.

6. Plant north and true north are essentially the same at SSES.

7. Other input is referenced as appropriate throughout the analysis.

4.0 METHODOLOGY The X/Q's for the SSES CRHE external cloud dose 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 x/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 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).

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus (XLQ}

Sh. No.

8 Checked By R.E. Anderson Table 1 - Inputs required for ARCON96 Meteorological Input Receptor Input Number of Met Data Files Distance to receptor Lower Measurement Height Receptor Location 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 366 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 Measurement Heights are 10m and 60 m, respectively, and the Wind Speed units are mph (Reference 2).

PP&L CALCULATION SHEET Dept.

0341 Rad & EffTech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No.. EC-ENVR-1058 Designed By M. M. Waselus

-(3Q}

Sh. No.

9 Checked By R.E. Anderson Source Input Three Source (or Release) points are analyzed. 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 (2) 874.7 198.7 60.6 11 4

Turbine Building Unit 2 exhaust vent (2) 874.7 198.7 60.6 11 5

Standby Gas Treatment System exhaust vent (2) 874.7 198.7 60.6 11

1. Release height = Release elevation (ft) - 676 ft (grade elevation for CRHE Structure).

2. Release height set = to 36.9 m or 121 feet in ARCON96 which is representative of the upper portion of the CRHE external walls. The height of the CRHE structure above grade is 134 feet.

The Building Area used for determining the wake effects is 2685 m2 per Reference 5 (included as ).

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 external walls. The point selected is approximately located at column lines L and 32 which is on the south wall of the CRHE structure (References 7, 8). Grade elevation for the SSES site at the Control Building is 676' (Reference 9).

With the combinations of release points and receptor location identified, the direction and distance between the release point and the receptor 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).

PP&L CALCULATION SHEET Dept.

0341 Rad & EffTech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors CaIc. No. EC-ENVR-1058 Designed By M.M. Waselus (tLO)

Sh. No.

10 Checked By R.E. Anderson The direction input to ARCON96 is the wind direction that would carry the plume from the release point to the receptor. For example, an analyst standing at the receptor location 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 receptor location. 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 receptor location 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., "taut string length"). The resulting source-to-receptor horizontal distances and direction are listed in Table 3. The values were determined by scaling from the reference drawings.

Table 3 - Release Point Horizontal Distances and Directions Description Horizontal Distance I Direction I Reference 3

TB Unit 1 exhaust vent 23.5 4

TB Unit 2 exhaust vent 19.0 5

SGTS exhaust vent 22.3 In accordance with Reference 3, section 3.4, taut string distances are determined below for the release points.

PP&L CALCULATION SHEET Dept.

0341 Rad & EffiTech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus (x.Q)

Sh. No.

11.

Checked By R.E. Anderson 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:

Figure 1 North

ýA TB U2 9-LPT 8-LP TB U1 12 Receptor Location 11 CRHE 10 7

4 3 6 5

RB U2 RB U1 2 1

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors CaIc. No. EC-ENVR-1058 Designed By M. M. Waselus fxLQ)

Sh. No.

12 Checked By R.E. Anderson The approximate roof elevations for the structures are listed as follows:

1. Control Building 810' Reference 9

2. Reactor Building 872' Reference 11 These elevations are used in determining the "taut string lengths" in accordance with Reference 3, Section 3.4. A simple schematic of each of these release points is provided in the following sketches.

Release points #3, 4, 5 TB 1 & 2 vents and SGTS vent (References 11, 12, 13 and 14).

TB & SGTS Vent 874.7 Reactor Building Roof 872 CB Roof8I0' Representative Receptor

~Location Reactor Elevation 797' Building Taut String Designation Reactor Buildin.-

Grade Elevation 670' Control Building Grade Elevation 676'

PP&L CALCULATION SHEET Dept.

0341 Rad & EffTech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus (LXQ)

Sh. No.

13 Checked By R.E. Anderson The following provides an example of the calculation of the taut string distance using the SGTS exhaust vent.

d (ft) = RB roof + CB roof + Ah where:

RB roof = ((RB hor. dist.)2 + (SGTS elevation - RB roof elevation)2)112

= ((28.93')2 + (874.7'-872')2)112 = 29.05' CB roof = ((CB hor. dist.)2 + (RB roof elevation - CB roof elevation) 2)1/2

= ((44.36')2 + (872'-810')2)1/2 = 76.2' Ah = CB roof elevation-CR receptor elevation = 810' - 797' = 13' Therefore, d(ft) = 29.05' + 76.2' + 13' = 118.3' or 36.1 m The distances for the remaining release points were similarly calculated and the results are shown on Attachment 1 (EXCEL file). Attachment 2 shows the formula version of the EXCEL file.

A summary of the resulting values from Attachment 1 is provided in Table 4.

Table 4 - Taut String Distances (meters)

Location Horizontal Distance Taut String Distance meters meters Table 3 3

Turbine Building Unit 1 exhaust vent 23.5 36.3 4

Turbine Building Unit 2 exhaust vent 19.0 33.3 5

Standby Gas Treatment System 22.3 36.1 exhaust vent

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058 Designed By M. M. Waselus Q

Sh. No.

14 Checked By R.E. Anderson 5.0 RESULTS The results of the analysis are provided on the ARCON96 computer outputs (Attachments 3, 4, 5 and 7) and summarized on Table 5.

Table 5 - CRHE X/Q's as a Function of Release Point without Occupancy Correction 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 Release Point sec/m 3 sec/m 3 sec/m 3 sec/m 3 sec/m 3 file 3

TB Unit 1 Exhaust Vent 4.03E-03 3.61E-03 1.56E-03 1.12E-03 8.71E-04 TB1EVZZ.log 4

TB Unit 2 Exhaust Vent 4.72E-03 4.25E-03 1.84E-03 1.32E-03 1.03E-03 TB2EVZZ.log 5

SGTS Exhaust Vent 4.15E-03 3.61E-03 1.57E-03 1.12E-03 8.86E-04 SGTSEVZZ.Iog 4A B Unit 2 Exhaust Vent 5.27E-03 4.13E-03 1.70E-03 1.21 E-03 1.02E-03 TB2ZZAZ.Iog To investigate the effects of having the receptor location at a different location of the CRHE structure, the ARCON96 model for the TB Unit 2 Exhaust Vent was rerun using the same input as Attachment 4 (south wall of CRHE structure) except the azimuth was changed from 250 to 2050, representative of the north wall. The results are shown as point 2A above. Comparing the two sets of values from Attachment 4 and Attachment 7, it is seen that except for the 0 to 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> time period the location on the south wall provides a conservative set of X/Q's for the calculation of radiological consequences. The dose contribution during the first two hours of the postulated LOCA is not significant compared to the total 30 day integrated dose.

PP&L CALCULATION SHEET Dept.

0341 Rad & Eff Tech.

PROJECT Date 11/10/06 CRHE Accident Dispersion Factors CaIc. No. EC-ENVR-1058 Designed By M. M. Waselus (7/)

Sh. No.

15 Checked By R.E. Anderson

6.0 REFERENCES

1. NUREG/CR-6331, Atmospheric Relative Concentrations in Building Wakes, Revision 1, May, 1997 (ARCON96 computer code).

2. EC-ENVR-1057, Offsite x/Q 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, June 2001.

5. SSES PLE-23733 included as Attachment 6.

6. USNRC Regulatory Guide 1.183, Alternative 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-105004 Sheet 7 Revision 27.

12. PPL Drawing E-106454 Sheet 14 Revision 11.

13. PPL Drawing E-1 06458 Sheet 14 Revision 8.

14. PPL Drawing E-106429-8 Revision 16.

15. PPL Drawing E-106429-10 Revision 15.

16. FSAR Figure 6.4-2. Revision 49.

17. PPL Drawing E-1 05004 Sheet 4 Revision 25.

18. PPL Drawing E-1 05007 Sheet 1 Revision 9.

19. PPL Drawing E-105618 Revision 1.

20. PPL Drawing E-1 05670 Revision 8.

21.PPL Drawing E-105005 Sheet 1 Revision 9.

22. PPL Drawing E-105004 Sheet 3 Revision 26.

23. PPL Drawing E-105004 Sheet 6 Revision 22.

24. EC-RADN-1 128, Steam Line Break Accident CRHE and Off Site Doses - AST, Revision 1.

EC-ENVR-1058 Attachment I Page 16 - EXCEL File - Taut String Distances

EC-ENVR-1058 Attachment I Page 17 Bc D

I E I

F G

1 2

3 4

5 6

7 8

9 10 11 12 13 14 taut d ft string dm Reference Distances distance ft TB 1 vent horizontal TB1 vent across RB roof TB1 vent across CB roof TB 2 vent horizontal TB2 vent across RB roof TB2 vent across CB roof SGTS horizontal.

SGTS vent across RB roof SGTS vent across CB roof 77.14 24.43 52.71 62.36 22.50 39.86 73.29 28.93 44.36 distance m 23.5 7.4 16.1 19.0 6.9 12.2 22.3 8.8 13.5 11,14 119.0 36.3 11,14 109.4 33.3 11,14 118.3 36.1

EC-ENVR-1058 Page 18 - EXCEL File (Formula)- Taut String Distances

EC-ENVR-1058 Page 19 AI B

C D

E F

G 1

8 3 5 6

7

-if 10

.. i]bisaa-ces taut d ft distance ft distance m string Reference dm 1

2 TB 1 vent horizontal

-TB1 vent across RB roof TB1 vent across GB roof TB 2 vent horizontal TB2 vent across RB.roof TB2 vent across CB roof SGTS horizontal SGTS vent across RB roof SGTS vent across CB roof 77.14 24.43 52,71 62.36 22.5 39.86

-C4/3.28

=C5/3.28

-=C6/3.28

=((C5A2)+(2,7A2))A0.5+((C6A2)+(62A2))A0.5+(13)

=E6/3.28 11,14

=C8/3.28

=C9/3.28

=C10/3.28.

=((C9A2)+(2.7A2))AO.5+((C1J0A2)+(62A2))AO.5+(13)

=E10/3.28 11,14 73.29

.=C12/3.28 28.93

=C13/3.28 11,14 44.36

=C14/3.28

=((C13 3A2)+(2.7 A2) )A 05+((C14A2)+(62 A2))A0.5+(13)

=E14/3.28

EC-ENVR-1058 Page 20 - TBIEVZZ.Iog ARCON96 Output for Turbine Building Unit 1 Exhaust Vent

EC-ENVR-1058 TBIEVZZ. log Page 21 Program

Title:

ARCON96.

Developed For:

Date:

U.S.

Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.

J.

Y. Lee Phone:

(301) 415 1080 e-mail: jyll@nrc.gov

.J. J.

Hayes Phone:

(301) 415 3167 e-mail: jjh@nrc.gov L.

A Brown Phone:

(301) 415 1232 e-mail: lab2@nrc.gov NRC Contacts:

Code Developer: J.

V.

Ramsdell Phone:

(509) 372 6316 e-mail: jramsdell@pnl.gov Code Documentation:

NUREG/CR-6331 Rev.

1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 8/

8/2006 at 11:47:52 ARCON INPUT ******

Number of Meteorological Data Files

=

Meteorological Data File Names C:\\ARCON96\\SQ99_0-I.MET Height of lower wind instrument (m)

=

Height of upper wind instrument (m)

=

Wind speeds entered as miles per hour Ground-level release Release height (m)

Building Area (m^2)

Effluent vertical velocity (m/s)

=

Vent or stack flow (m^3/s)

=

Vent or stack radius (m)

Direction.. intake to source (deg)

=

Wind direction sector width (deg)

=

Wind direction window (deg)

=

Distance to intake (m)

Intake height (m)

Terrain elevation difference (m)

Output file names tblevzz..log tblevzz.cfd 10.0 60.0 36.9 2685.0

.00

.00

.00 021 90 336 - 066 36.3 36.9

.0 Minimum Wind Speed (mIs)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

.20 4.3

,00

.00 Expanded output for code testing not selected Total number of hours of data processed =

Hours of missing data Hours direction in window Hours elevated plume w/ dir. in window Hours of calm winds Hours direction not in window or calm 43824 297 15313 0

757 27457 DISTRIBUTION AVER.

PER.

UPPER LIM.

LOW LIM.

ABOVE RANGE IN RANGE BELOW RANGE ZERO TOTAL X/Qs

% NON ZERO

SUMMARY

DATA BY AVERAGING INTERVAL 1

2 4

8 1.OOE-02 1.00E-02 1.OOE-02 1.OE-02 1.OOE-06 1.OOE-06 1.00E-06 1.OOE-06

0.

0.

0.

0.

16070.

18373.

21580.

26323.

• 0.

0.

0.

0.

27457.

25108.

21822.

16933.

43527.

43481.

43402.

43256.

36.92 42.26 49.72 60.85 12 24 96 1.OOE-02 1.OOE-02 l.OOE-02 1.OOE-06 1.00E-06 l.OOE-06

0.

0.

0.

30094.

36190.

42766.

0.

0.

0.

13206.

6963.

191.

43300.

43153.

42957.

69.50 83.86 99.56 168

1. OOE-02

1. OOE-06 0.

42621.

0.

0.

42621.

100.00 360 1.OOE-02 1.00E-06 0.

42457.

0.

0.

42457.

100.00 720

1. OOE-02 1.O0E-06 0.

43155.

0.

0:

43155.

100.00 95th PERCENTILE X/Q VALUES 4.03E-03 3.95E-03 3.87E-03

.3.71E-03 3.08E-03 2.28E-03 1.41E-03 1.19E-03 1.04E-03 9.43E-04 95% X/Q for standard averaging intervals

EC-ENVR-1058 Page 22 0

2 8

1 4

to *2 hours to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 4 days to 30 days CENTERLINE SECTOR-AVERAGE

4. 03E-03

3. 61E-03

1. 56E-03

1. 12E-03

8. 71E-04 HOURLY VALUE RANGE MAX X/Q 5.46E-03 3.18E-03 MIN X/Q

6. 32E-04

3. 68E-04 NORMAL PROGRAM COMPLETION

EC-ENVR-1058 Page 23 - TB2EVZZ.Iog ARCON96. Output for Turbine Building Unit 2 Exhaust Vent

EC-ENVR-1058 TB2EVZZ. log Page 24 Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.

Date:

NRC Contacts:

J.

Y. Lee Phone:

(301) 415 1080 e-mail: jyll@nrc.gov J.

J.

Hayes Phone:

(301) 415 3167 e-mail: jjh@nrc.gov L.

A Brown Phone:

(301) 415 1232 e-mail: lab2@nrc.gov Code Developer:

J.

V.

Ramsdell Phone:

(509) 372 6316 e-mail: jramsdell@pnl.gov Code Documentation:

NUREG/CR-6331 Rev.

1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 8/

8/2006 at 11:49:02

• ARCON INPUT

• Number of Meteorological Data Files

=

1 Meteorological Data File Names C:\\ARCON96\\SQ99_0-I.MET Height of lower wind instrument (m)

=

Height of upper wind instrument (m)

=

Wind speeds entered as miles per hour 10.0 60.0 Ground-level release Release height (i)

=

36.9 Building Area (m^2).

=

2685.0 Effluent vertical velocity (m/s)

=

.00 Vent or stack flow.

(m^3/s)

=

.00 Vent or stack radius (m)

.00 Direction.. intake to source (deg)

=

025 Wind direction sector width (deg)

=

90 Wind direction window (deg)

=

340 -

070 Distance to intake (m)

=

33.3 Intake height (m)

=

36.9 Terrain elevation difference (m)

=

.0 Output file names tb2evzz.log tb2evzz.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5

=

.20

=

4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed =

Hours of missing data Hours direction in window Hours elevated plume w/ dir. in window

=

Hours of calm winds Hours direction not in window or calm 43824 297 15284 0

757 27486 DISTRIBUTION SUM4MARY DATA BY AVERAGING INTERVAL AVER.

PER.

1 2

4 8

UPPER LIM.

1.00E-02 1.00E-02 1.00E-02 1.OOE-02 LOW LIM.

1.00E-06 1.00E-06 1.OOE-06 1.OOE-06 ABOVE RANGE

0.

0.

0.

0.

IN RANGE 16041.

18313.

21485.

26194.

BELOW RANGE

0.

0.

0.

0.

ZERO 27486.

25168.

21917.

17062.

TOTAL X/Qs 43527.

43481.

43402.

43256.

% NON ZERO 36.85 42.12 49.50 60.56 12

1. OOE-02

1. OOE-06 0.

29957.

0.

13343.

43300.

69.18 24 1.OOE-02 1.OOE-06 0.

36050.

0.

7103.

43153.

83.54 96 168 1.OOE-02 1.OOE-02 1.00E-06 1.OOE-06

0.

0.

42764.

42621.

360

1. OOE-02

1. OOE-06 0.

42457.

0.

0.

42457.

100.00 720

1. OOE-02

1. OOE-06 0.

43155.

0.

0.

43155.

100.00 0.

193.

42957.

99.55 0.

0.

42621.

100.00 95th PERCENTILE X/Q VALUES 4.72E-03 4.68E-03 4.58E-03 4.37E-03 3.62E-03 2.68E-03 1.66E-03 1.41E-03 1.22E-03 1.11E-03

EC-ENVR-1058 Page 25 95% X/Q for standard averaging intervals 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 4. 72E-03

4. 25E-03 1.84E-03

1. 32E-03 1.03E-03 HOURLY VALUE RANGE MAX X/Q MIN X/Q 6.46E-03 7.43E-04 3.76E-03 4.33E-04 CENTERLINE SECTOR-AVERAGE NORMAL PROGRAM COMPLETION

EC-ENVR-1058 Page 26 - SGTSEVZZ.Iog ARCON96 Output for Standby Gas Treatment System Exhaust Vent

EC-ENVR-1058 Page 27 SGTSEVZZ.log Program

Title:

ARCON96.

Developed For:

U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management Date:

June 25, 1997 11:00 a.m.

NRC Contacts:

J.

Y. Lee Phone:

(301) 415 1080 e-mail: jyll@nrc.gov J.

J.

Hayes Phone:

(301) 415 3167 e-mail: jjh@nrc.gov L.

A Brown Phone:

(301) 415 1232 e-mail: lab2@nrc.gov Code Developer: J.

V.

Ramsdell Phone:

(509) 372 6316 e-mail: j_ramsdell@pnl.gov Code Documentation:

NUREG/CR-6331 Rev.

1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run B/ 8/2006 at 11:55:48 a*asses ARCON INPUT***********

Number of Meteorological Data Files

=

1 Meteorological Data File Names C:\\ARCON96\\SQ99_0-I.MET Height of lower wind instrument (m)

=

10.0 Height of upper wind instrument (m)

=

60.0 Wind speeds entered as miles per hour Ground-level release Release height (i) 36.9 Building Area (m^2) 2685.0 Effluent vertical velocity (m/s)

.00 Vent or stack flow (m^3/s)

.00 Vent or stack radius (m)

.00 Direction.. intake to source (deg) 027 Wind direction sector width (deg) 90 Wind direction window (deg) 342 -

072 Distance to intake (m) 36.1 Intake height (m) 36.9 Terrain elevation difference (m)

.0 Output file names sgtszz.log sgtszz.cfd Minimum Wind Speed (m/s)

.5 Surface roughness length (m)

.20 Sector averaging constant 4.3 Initial value of sigma y

.00 Initial value of sigma z

.00 Expanded output for code testing not selected Total number of hours of data processed =

43824 Hours of missing data 297 Hours direction in window 15267 Hours elevated plume w/ dir. in window 0

Hours of calm winds 757 Hours direction not in window or calm 27503 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER.

PER.

1 2

4 8

12 24 96 168 360 720 UPPER LIM.

1.OOE-02 1.OOE-02 1.OOE-02 1.00E-02 1.00E-02 1.00E-02 1.OOE-02 1.00E-02 l.00E-02 1.OOE-02 LOW LIM.

1.OOE-06 1.00E-06 1.OOE-06 1.00E-06 1.00E-06 1.OE-06 1.00E-06 1.00E-06 1.OOE-06 1.00E-06 ABOVE RANGE

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

IN RANGE 16024.

18280.

21437.

26142.

29906.

35987.

42772.

42621.

42457.

43155.

BELOW RANGE

0.

0.

0.

0.

0.

0.

0.

0.

0.

0.

ZERO 27503.

25201.

21965.

17114.

13394.

7166.

185.

0.

0.

0.

TOTAL X/Qs 43527.

43481.

43402.

43256.

43300.

43153.

42957.

42621.

42457.

43155.

% NON ZERO 36.81 42.04 49.39 60.44 69.07 83.39 99.57 100.00 100.00 100.00 95th PERCENTILE X/Q VALUES 4.15E-03 4.02E-03 3.91E-03 3.74E-03 3.11E-03 2.29E-03 1.42E-03 1.21E-03 1.05E-03 9.56E-04 95% X/Q for standard averaging intervals

EC-ENVR-1058 Page 28 0

2 4

1 4

to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to 4 days to 30 days CENTERLINE SECTOR-AVERAGE 4.15E-03 3. 61E-03

1. 57E-03 1. 12E-03

8. 8 6E-04 HOURLY VALUE RANGE MAX X/Q 5.52E-03 3.22E-03 MIN X/Q

6. 39E-04

3. 72E-04 NORMAL PROGRAM COMPLETION

EC-ENVR-1058 Page 29 - PLE-23733 - Cross Sectional Area

EC-ENVR-1058 Page 30 PPL Susquehanna, LLC I ',' No,'h NmI; N) N)!-

,ik-I;,l! IA

,1101-i 7' lic. 6II*77-.1.7 V za tK, 0.*,7.i772 4-November 5. 2004 Mr. Mark Abrams ABS Consulting, Inc.

4 Research Place Suite 200 Rockville, MD 20850 SUSQUEHANNA STEAM ELECTRIC STATION CONTROL ROOM ACCIDENT X/Q ANALYSIS PLE-23733

Dear Mr. Abrams:

Attached for your use is our evaluation of the minimum vertical cross-sectional area of the reactor building for your use in evaluating accident atmospheric dispersion factors.

Also attached are the SSES design drawings referenced in the analysis. Please review and verify that the attached analysis is appropriate for the accident /,/Q analysis. Keith Woodard had indicated in a previous discussion that it may be possible to include this rninimum area analysis in your x/Q calculation. If you cannot, please let me know since we will then need to formalize the minimum area analysis in a formal PPL calculation.

Please contact me at 610-774-4717 if you need additional information. My email address is tfmackay@ pplweb.com.

Sincerely, Terrence F. Mackay Senior Engineer - Rad & Effl Technology.

Analysis Of Vertical Cross-Sectional Area (Minimuml) 0 Reactor Butiding For Evaluation Of //Q's..

SSES Design Drawings:

E106312, Revision F (AE Dwg. M-207 E105004, Sheet 6. Revision 22: AE Dwg. A-16)

E105007, Sheet 1, Revision 9 (AE Dwg. A-21, Sht. 1)

EC-ENVR-1058 Page 3)1 November 5. 2004 PLE-23733 Page 2 of 2 E105329, Revision 9 (AE Dwg. C-322)

E105257, Revision 9 (AE Dwg. C-227)

El 05259, Revision 8 (AE Dwg. C-229) cc: w/ Att. 1 only:

R.A. Vazquies Francis J. Hickey R.L. Doty D.G. Kostelnik Nuclear Records GENPL5 NUCSA3 GENPL5 GENPL5 GENPL4 gAgoadmin~ide eIec~doty.tfrn'ple-23733.doc

EC-ENVR-1058 Page '32 November 5, 2004 PLE-23733 Attachment 1 Page 1 of 2 Analysis Of Vertical Cross-Sectional Area (Minimum)

Of Reactor Building For Evaluation Of y/Q's The general arrangement of the reactor building is shown in SSES design drawing E106312, Revision F (AE Dwg. M-207). 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; AE Dwg. A-16). 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 (AE Dwg. A-21, Sht. 1)

El 05329, Revision 9 (AE Dwg. C-322)

Reactor Building Roof Elevation = 873'-112,873.12 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 ft2

2.

Reactor Building Bottom Of Superstructure to Turbine Building Roof Elevation

References:

SSES Drawings E105007, Sheet 1, Revision 9 (AE Dwg. A-21, Sht. 1)

E105329, Revision 9 (AE Dwg. C-322)

El 05257, Revision 9 (AE Dwg. C-227)

E105259, Revision 8 (AE Dwg. C-229)

Superstructure Bottom Elevation = 809'- 7 5/8" = 809.64 ft Turbine Building Roof Elevation = 789'-8/4" = 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'-0")

+(16'-0") + (V'-9 5/16")

Width = 153.28 ft Area = 19.91 ft X 153.28 ft = 3052 ft2

EC-ENVR-1058 Attachm~ent 6 Page 33)

November 5, 2004 PLE-23733 Attachment 1 Page 2 of 2 Analysis Of Vertical Cross-Sectional Area (Minimum)

Of Reactor Building For Evaluation Of y/Q's

3.

Turbine Building Roof Elevation to Grade Elevation

References:

SSES Drawings El 05007, Sheet 1, Revision 9 (AE Dwg. A-21, Sht. 1)

El 05257, Revision 9 (AE Dwg. C-227)

El 05259, Revision 8 (AE Dwg. C-229)

.Turbine Building Roof Elevation = 789'-83 "= 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")+(1 '-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 ft2 + 3052 ft 2 + 15581 ft 2 Total Area = 28906 ft2 x (.0929 m2 / ft2) = 2685 m2

EC-ENVR-1058 Page 34 - TB2ZZAZ.Iog ARCON96 Output for Turbine Building Unit 2 Exhaust Vent Evaluating Azimuth Change

EC-ENVR-1058 Program

Title:

ARCON96.

Page 35 Developed For:

Date:

NRC Contacts:

Code Developer:

UýS.

Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Reactor Program Management June 25, 1997 11:00 a.m.

J.

Y. Lee Phone:

(301) 415 1080 e-mail: jyll@nrc.gov J.

J.

Hayes Phone:

(301) 415 3167 e-mail: jjh@nrc.gov L.

A Brown Phone:

(301) 415 1232 e-mail: lab2@nrc.gov J.

V. Ramsdell Phone:

(509) 372 6316 e-mail: jramsdell@pnl.gov Code Documentation:

NUREG/CR-6331 Rev.

1 The program was prepared for an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, expressed or implied, or assumes any legal liability or responsibilities for any third party's use, or the results of such use, of any portion of this program or represents that its use by such third party would not infringe privately owned rights.

Program Run 10/

7/2006 at 14:09:52 5******

ARCON INPUT**********

Number of Meteorological Data Files

=

Meteorological Data File Names C:\\ARCON96\\SQ99_0-~.MET Height of lower wind instrument (m)

=

Height of upper wind instrument (m)

=

Wind speeds entered as miles per hour 1

10.0 60.0 Ground-level release Release height (m)

Building Area (Wn2)

Effluent vertical velocity (mIs)

Vent or stack flow (m^3/s)

Vent or stack radius (m)

Direction.. intake to source (deg)

Wind direction sector width (deg)

Wind direction window (deg)

Distance to intake (m)

Intake height (m)

Terrain elevation difference (m)

=

36.9

=

2685.0

.00

=

.00

.00

=

205 90

=

160 -

250

=

33.3

=

36.9

.0 Output file names tb2zzaz.log tb2zzaz.cfd Minimum Wind Speed (m/s)

Surface roughness length (m)

Sector averaging constant Initial value of sigma y Initial value of sigma z

.5.

.20

=

4.3

.00

.00 Expanded output for code testing not selected Total number of hours of data processed =

Hours of missing data Hours direction in window

.=

Hours elevated plume w/ dir. in window

=

Hours of calm winds Hours direction not in window or calm

=

43824 297 i5024 0

757 27746 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER.

PER.

1 2

4 8

UPPER LIM.

1.00E-02 1.O0E-02 1.OOE-02 1.00E-02 LOW LIM.

1.00E-06 1.00E-06 1.00E-06 1.OOE-06 ABOVE RANGE

0.

0.

0.

0.

. IN RANGE 15781.

18576.

22279.

27067.

BELOW RANGE

0.

0.

0.

0.

ZERO 27746.

24905.

21123.

16189.

TOTAL X/Qs 43527.

43481.

43402.

43256.

% NON ZERO 36.26 42.72 51.33 62.57 12 1.00E-02

1. OOE-06 0.

30564.

0.

12736.

43300.

70.59 24 96 168 1.00E-02 1.OE-02 1.0oC-02 1.OOE-06 1.OOE-06 1.00E-06

0.

0.

0.

36401.

42669.

42583.

0.

0.

0.

6752.

288.

38.

43153.

42957.

42621.

84.35 99.33 99.91 360 1.00E-02 1.00E-06 0.

42457.

0..

0.

42457.

100.00 720

1.

OOF-02 1.00E-06 0.

43155.

0.

0.

43155.

100.00 95th PERCENTILE X/Q VALUES" 5.27E-03 5.04E-03 4.77E-03 4.41E-03 3.58E-03 2.60E-03 1.56E-03 1.38E-03 1.20E-03 1.09E-03 95% X/Q for standard averaging intervals

EC-ENVR-1058 Page 36 0

2 4

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 CENTERLINE SECTOR-AVERAGE 5.27E-03

4. 13E-03

1. 70E-03 1.21E-03

1. 02E-03 HOURLY VALUE RANGE MAX X/Q MIN X/Q 6.98E-03 4.78E-04 4.07E-03 2.79E-04 NORMAL PROGRAM COMPLETION