Attachment 4 to PLA-6124 EC-ENVR-1058, Revision I · Yes, Re/er to NDAP-QA-0730 and NDAP-QA-0731 El...

Attachment 4 to PLA-6124

EC-ENVR-1058, Revision I

PCAF 42005-1237Page 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 SUPERSEDED BY: N/A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(oPrinit 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 Date7.8 of NEPM-OA-t022!1)

20. Accepted by: '. \Thr /Print Name (EG771 Qualification Required) and coanmpi with Signature -se DateSection 7.9 of NEPM-QA-0221

ADD A NEW COVER PAGE FOR EACH REVISIONFORM NEPM-QA-0221-1, Revision 9, Page I of I, ELECTRONIC FORM

* Verified Fields

> REQUIRED FIELDS

CALCULATION REVISION DESCRIPTION SHEETNEPM-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[] FULL REVISION I- SUPERSEDED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 DescriptionPages d p m of Revision on the Listed Pages

d I vAll - Total revision

[ D _-1 [__

El F] 71:

__ DF-1El F-1 El]

E-3 i-1 -1:

Elq F-1 E

ED n nE DD

n El_____ D--D

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

TECHNICAL CHANGE SUMMARY PAGENEPM-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 thescope of verification if the calculation was verified. It should not be more than one page. Itspurpose is to provide summary information to the reviewer, verifier, approver, and acceptorabout the technical purpose of the change. For non-technical revisions, state the purpose orreason for the revision.

Scope of Revision: Revision 1 is a total revision to the calculation. Revision 1 corrects theunits 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 SHEETDept. 0341 Rad & Eff Tech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed By M. M. Waselus -XLQ) Sh. No. 4Checked By R.E. Anderson

TABLE OF CONTENTS

1.0 PURPOSE ................. .................................................... 52.0 CONCLUSIONS AND RECOMMENDATIONS ...................................... 63.0 A S SU M PT IO N S / IN PU T .................................................................. ......................................................... 64.0 METHODOLOGY 7...................... ................................... 75.0 RESULTS ................................................................ 146 .0 R E F E R E N C E S ........................................................................................................................................ 15Attachment 1 - EXCEL File - Taut String Distances ........................................ 16Attachment 2 - EXCEL File (Formula)- Taut String Distances ...................................................................... 18Attachment 3 - TB I EVZZ.Iog ........................................................ 20Attachment 4 - TB2EVZZ.Iog ........................................................ 23A ttachm ent 5 - SG T SEV ZZ.log..................................................... ................................................. 26Attachment 6 - PLE-23733 - Cross Sectional Area ......................................... 29Attachment 7 - TB2ZZAZ.Iog ........................................................ 34

PP&L CALCULATION SHEETDept. 0341 Rad & Eff Tech. PROJECT

Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed 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. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Caic. No. EC-ENVR-1058Designed By M. M. Waselus /_(Q) Sh. No. 6


References 7 to 23 provide details of the layout of the SSES plant structures, exhaust ventsand components. By inspection of the locations of the potential release points relative to thelocation 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 detailherein. The Reactor Building exhaust vents (release points 1 & 2) are not a source of postLOCA activity releases. The Reactor Building closest distance (release points 6 & 7) wouldonly 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, elevation729') are bounded by the Turbine Building exhaust vents (release points 3 & 4) which areoverall closer to the CRHE walls. The Reactor Building and Turbine Building. Unit 1 blowoutpanels (release points 10 & 12) and the Reactor Building and Turbine Building Unit 2 blowoutpanels (release points 11 & 13) are not required to be evaluated herein since they only pertainto the Main Steam Line Break and are evaluated in EC-RADN-1 128 (Reference 24). SeeFigure 1 on page 11 for the relative locations of the 13 release points and the CRHE outsideair intake. The specific locations requiring ARCON96 7/Qs for use in the applicableradiological 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 CONCLUSIONS AND RECOMMENDATIONS

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

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

]Time Period 0to2 hours 2to8 hours 8to24hours 1 to4days 4to30days3 TB Unit 1 Exhaust Vent 4.03E-03 3.61E-03 1.56E-03 1.12E-03 8.71E-044 TB Unit 2 Exhaust Vent 4.72E-03. 4.25E-03 1.84E-03 1.32E-03 1.03E-035 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 SHEETDept. 0341 Rad & EffTech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed By M. M. Waselus (EQ.) Sh. No. 7Checked 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 SHEETDept. 0341 Rad & Eff Tech. PROJECT

Date 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed By M. M. Waselus (XLQ} Sh. No. 8Checked By R.E. Anderson

Table 1 - Inputs required for ARCON96Meteorological Input Receptor InputNumber of Met Data Files Distance to receptorLower Measurement Height Receptor Location HeightUpper Measurement Height Elevation DifferenceWind Speed Direction to SourceSource InputRelease Type Output FilesRelease Height Output File Name fn.logBuilding Area CFD File Name fn.cfdVertical Velocity Expanded Output noStack FlowStack 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 SHEETDept. 0341 Rad & EffTech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Calc. No.. EC-ENVR-1058Designed By M. M. Waselus -(3Q} Sh. No. 9


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 ReferenceElevation, 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

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 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 SHEETDept. 0341 Rad & EffTech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors CaIc. No. EC-ENVR-1058Designed By M.M. Waselus (tLO) Sh. No. 10Checked 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.


Dept. 0341 Rad & EffiTech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed By M. M. Waselus (x.Q) Sh. No. 11.


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 U29-LPT 8-LP

TB U1

12

Receptor Location

11

CRHE

107 4 3 6

5

RB U2 RB U1

2 1

PP&L CALCULATION SHEETDept. 0341 Rad & Eff Tech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors CaIc. No. EC-ENVR-1058Designed By M. M. Waselus fxLQ) Sh. No. 12Checked 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 874.7Reactor BuildingRoof 872

CB Roof8I0'

Representative Receptor~Location

Reactor Elevation 797'Building

Taut String Designation

Reactor Buildin.-Grade Elevation 670'

Control BuildingGrade Elevation 676'

PP&L CALCULATION SHEETDept. 0341 Rad & EffTech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed By M. M. Waselus (LXQ) Sh. No. 13


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 metersTable 3 Attachment 1

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 36.1exhaust vent


Dept. 0341 Rad & Eff Tech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors Calc. No. EC-ENVR-1058Designed By M. M. Waselus Q Sh. No. 14Checked 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 hours 2 to 8 hours 8 to 24 hours 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 file3 TB Unit 1 Exhaust Vent 4.03E-03 3.61E-03 1.56E-03 1.12E-03 8.71E-04 TB1EVZZ.log Attachment 3

4 TB Unit 2 Exhaust Vent 4.72E-03 4.25E-03 1.84E-03 1.32E-03 1.03E-03 TB2EVZZ.log Attachment 4

5 SGTS Exhaust Vent 4.15E-03 3.61E-03 1.57E-03 1.12E-03 8.86E-04 SGTSEVZZ.Iog Attachment 5

4A B Unit 2 Exhaust Vent 5.27E-03 4.13E-03 1.70E-03 1.21 E-03 1.02E-03 TB2ZZAZ.Iog Attachment 7

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 hour 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 SHEETDept. 0341 Rad & Eff Tech. PROJECTDate 11/10/06 CRHE Accident Dispersion Factors CaIc. No. EC-ENVR-1058Designed By M. M. Waselus (7/) Sh. No. 15Checked By R.E. Anderson

6.0 REFERENCES1. 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 RoomRadiological Habitability Assessments at Nuclear Power Plants, June, 2003.

4. NEI-99-03, Control Room Habitability Assessment Guidance, Nuclear Energy Institute, June2001.

5. SSES PLE-23733 included as Attachment 6.

6. USNRC Regulatory Guide 1.183, Alternative Radiological Source Terms For EvaluatingDesign 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

Attachment 1 - EXCEL File - Taut String Distances

EC-ENVR-1058 Attachment I Page 17

Bc D I E I F G1

2

3

4

5

6

7

8

9

10

11

12

13

14

tautd ft

stringdm

ReferenceDistances distance ft

TB 1 vent horizontalTB1 vent across RB roofTB1 vent across CB roof

TB 2 vent horizontalTB2 vent across RB roofTB2 vent across CB roof

SGTS horizontal.SGTS vent across RB roofSGTS vent across CB roof

77.1424.4352.71

62.3622.5039.86

73.2928.9344.36

distance m

23.57.4

16.1

19.06.9

12.2

22.38.8

13.5

11,14

119.0 36.3

11,14

109.4 33.3

11,14

118.3 36.1

EC-ENVR-1058 Attachment 2 Page 18

Attachment 2 - EXCEL File (Formula)- Taut String Distances


AI B C D E F G1

8

3-4-567

-if

10

.. i]bisaa-cestautd ftdistance ft distance m

string Referencedm

1

2

TB 1 vent horizontal -TB1 vent across RB roof

TB1 vent across GB roof

TB 2 vent horizontalTB2 vent across RB.roofTB2 vent across CB roof

SGTS horizontalSGTS vent across RB roofSGTS vent across CB roof

77.14

24.4352,71

62.3622.539.86

-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 .=C12/3.2828.93 =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


Attachment 3 - TBIEVZZ.IogARCON96 Output

forTurbine Building Unit 1 Exhaust Vent

EC-ENVR-1058 Attachment 3

TBIEVZZ. log

Page 21

Program Title: ARCON96.

Developed For:

Date:

U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

June 25, 1997 11:00 a.m.

J. Y. Lee Phone: (301) 415 1080e-mail: [email protected]

.J. J. Hayes Phone: (301) 415 3167e-mail: [email protected]

L. A Brown Phone: (301) 415 1232e-mail: [email protected]

NRC Contacts:

Code Developer: J. V. Ramsdell Phone: (509) 372 6316e-mail: [email protected]

Code Documentation: NUREG/CR-6331 Rev. 1

The program was prepared for an agency of the United States Government. Neitherthe United States Government nor any agency thereof, nor any of theiremployees, makes any warranty, expressed or implied, or assumes any legalliability or responsibilities for any third party's use, or the results of suchuse, of any portion of this program or represents that its use by such thirdparty 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 releaseRelease 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 namestblevzz..logtblevzz.cfd

10.060.0

36.92685.0

.00

.00

.00

02190

336 - 06636.336.9

.0

Minimum Wind Speed (mIs)Surface roughness length (m)Sector averaging constant

Initial value of sigma yInitial value of sigma z

.5

.204.3

,00.00

Expanded output for code testing not selected

Total number of hours of data processed =

Hours of missing dataHours direction in windowHours elevated plume w/ dir. in windowHours of calm windsHours direction not in window or calm

43824297

153130

75727457

DISTRIBUTIONAVER. PER.UPPER LIM.

LOW LIM.ABOVE RANGE

IN RANGEBELOW RANGE

ZEROTOTAL X/Qs% NON ZERO

SUMMARY DATA BY AVERAGING INTERVAL1 2 4 8

1.OOE-02 1.00E-02 1.OOE-02 1.OE-021.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 24 961.OOE-02 1.OOE-02 l.OOE-021.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

1681. OOE-021. OOE-06

0.42621.

0.0.

42621.100.00

3601.OOE-021.00E-06

0.42457.

0.0.

42457.100.00

7201. OOE-021.O0E-06

0.43155.

0.0:

43155.100.00

95th PERCENTILE X/Q VALUES4.03E-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


02814

to *2 hoursto 8 hoursto 24 hoursto 4 daysto 30 days

CENTERLINESECTOR-AVERAGE

4. 03E-033. 61E-031. 56E-031. 12E-038. 71E-04

HOURLY VALUE RANGEMAX X/Q

5.46E-033.18E-03

MIN X/Q6. 32E-043. 68E-04

NORMAL PROGRAM COMPLETION


Attachment 4 - TB2EVZZ.IogARCON96. Output


EC-ENVR- 1058 Attachment 4

TB2EVZZ. log

Page 24


Developed For: U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

June 25, 1997 11:00 a.m.Date:

NRC Contacts: J. Y. Lee Phone: (301) 415 1080e-mail: [email protected]

J. J. Hayes Phone: (301) 415 3167e-mail: [email protected]





Program Run 8/ 8/2006 at 11:49:02

*** *ARCON INPUT *

Number of Meteorological Data Files = 1Meteorological Data File Names



10.060.0

Ground-level releaseRelease height (i) = 36.9

Building Area (m^2). = 2685.0Effluent vertical velocity (m/s) = .00Vent or stack flow. (m^3/s) = .00Vent or stack radius (m) - .00

Direction .. intake to source (deg) = 025Wind direction sector width (deg) = 90Wind direction window (deg) = 340 - 070Distance to intake (m) = 33.3Intake height (m) = 36.9

Terrain elevation difference (m) = .0

Output file namestb2evzz.logtb2evzz.cfd

Minimum Wind Speed (m/s)Surface roughness length (m)Sector averaging constant


- .5= .20= 4.3

.00

.00



Hours of missing dataHours direction in window -

Hours elevated plume w/ dir. in window =

Hours of calm windsHours direction not in window or calm

43824297

152840

75727486

DISTRIBUTION SUM4MARY DATA BY AVERAGING INTERVALAVER. PER. 1 2 4 8UPPER 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-06ABOVE 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

121. OOE-021. OOE-06

0.29957.

0.13343.43300.69.18

241.OOE-021 .OOE-06

0.36050.

0.7103.

43153.83.54

96 1681.OOE-02 1.OOE-021.00E-06 1.OOE-06

0. 0.42764. 42621.

3601. OOE-021. OOE-06

0.42457.

0.0.

42457.100.00

7201. OOE-021. OOE-06

0.43155.

0.0.

43155.100.00

0.193.

42957.99.55

0.0.

42621.100.00

95th PERCENTILE X/Q VALUES4.72E-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



0 to 2 hours2 to 8 hours8 to 24 hours1 to 4 days4 to 30 days

4 . 72E-03

4. 25E-031 .84E-03

1. 32E-031 .03E-03

HOURLY VALUE RANGEMAX X/Q MIN X/Q

6.46E-03 7.43E-043.76E-03 4.33E-04

CENTERLINE

SECTOR-AVERAGE



Attachment 5 - SGTSEVZZ.IogARCON96 Output

forStandby Gas Treatment System Exhaust Vent

EC-ENVR- 1058 Attachment 5 Page 27

SGTSEVZZ.log


Developed For: U.S. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

Date: June 25, 1997 11:00 a.m.

NRC Contacts: J. Y. Lee Phone: (301) 415 1080e-mail: [email protected]

J. J. Hayes Phone: (301) 415 3167e-mail: [email protected]





Program Run B/ 8/2006 at 11:55:48

a*asses ARCON INPUT***********

Number of Meteorological Data Files = 1Meteorological Data File Names


Height of lower wind instrument (m) = 10.0Height of upper wind instrument (m) = 60.0Wind speeds entered as miles per hour

Ground-level releaseRelease height (i) 36.9

Building Area (m^2) 2685.0Effluent vertical velocity (m/s) .00Vent or stack flow (m^3/s) .00Vent or stack radius (m) .00

Direction .. intake to source (deg) 027Wind direction sector width (deg) 90Wind direction window (deg) 342 - 072Distance to intake (m) 36.1

Intake height (m) 36.9

Terrain elevation difference (m) .0

Output file namessgtszz.logsgtszz.cfd

Minimum Wind Speed (m/s) .5Surface roughness length (m) .20Sector averaging constant 4.3

Initial value of sigma y .00Initial value of sigma z .00


Total number of hours of data processed = 43824Hours of missing data 297Hours direction in window 15267Hours elevated plume w/ dir. in window 0Hours of calm winds 757Hours direction not in window or calm 27503

DISTRIBUTION SUMMARY DATA BY AVERAGING INTERVALAVER. PER. 1 2 4 8 12 24 96 168 360 720UPPER 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-06ABOVE 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 VALUES4.15E-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



0241

4

to 2 hoursto 8 hoursto 24 hoursto 4 daysto 30 days


4.15E-033 . 61E-031. 57E-031 . 12E-038. 8 6E-04

HOURLY VALUE RANGEMAX X/Q

5.52E-033.22E-03

MIN X/Q6. 39E-043. 72E-04


EC-ENVR- 1058 Attachment 6 Page 29

Attachment 6 - PLE-23733 - Cross Sectional Area


PPL Susquehanna, LLCI ',' 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 AbramsABS Consulting, Inc.4 Research PlaceSuite 200Rockville, MD 20850

SUSQUEHANNA STEAM ELECTRIC STATIONCONTROL ROOM ACCIDENT X/Q ANALYSISPLE-23733

Dear Mr. Abrams:

Attached for your use is our evaluation of the minimum vertical cross-sectional area ofthe reactor building for your use in evaluating accident atmospheric dispersion factors.Also attached are the SSES design drawings referenced in the analysis. Please reviewand verify that the attached analysis is appropriate for the accident /,/Q analysis. KeithWoodard had indicated in a previous discussion that it may be possible to include thisrninimum area analysis in your x/Q calculation. If you cannot, please let me know sincewe 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 emailaddress is tfmackay@ pplweb.com.

Sincerely,

.............. ..

Terrence F. MackaySenior Engineer - Rad & Effl Technology

Attachment 1. Analysis Of Vertical Cross-Sectional Area (Minimuml) 0 Reactor Butiding ForEvaluation Of //Q's.

Attachment 2. SSES Design Drawings:E106312, Revision F (AE Dwg. M-207E105004, Sheet 6. Revision 22: AE Dwg. A-16)E105007, Sheet 1, Revision 9 (AE Dwg. A-21, Sht. 1)

EC-ENVR-1058 Attachment 6 Page 3)1

November 5. 2004PLE-23733Page 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. VazquiesFrancis J. HickeyR.L. DotyD.G. KostelnikNuclear Records

GENPL5NUCSA3GENPL5GENPL5GENPL4

gAgoadmin~ide eIec~doty.tfrn'ple-23733.doc

EC-ENVR-1058 Attachment 6 Page '32

November 5, 2004PLE-23733 Attachment 1Page 1 of 2

Attachment 1

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 drawingE106312, Revision F (AE Dwg. M-207). Above the turbine building roof elevation,the reactor building area includes the superstructure area and the area associatedwith the blowout panels and duct spaces between Column Lines P and M (seeSSES design drawing E105004, Sheet 6, Revision 22; AE Dwg. A-16). Below theturbine building roof elevation, credit is only taken for the reactor building areabetween Column Lines U and P, including the concrete outer walls.

1. Reactor Building Roof to Bottom Of Superstructure

References: SSES DrawingsE105007, 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 ftSuperstructure 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 RoofElevation

References: SSES DrawingsE105007, 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 ftTurbine 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, 2004PLE-23733 Attachment 1Page 2 of 2

Attachment 1

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 DrawingsEl 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 ftGrade 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


Attachment 7 - TB2ZZAZ.IogARCON96 Output


Evaluating Azimuth Change

EC-ENVR-1058


Attachment 7 Page 35

Developed For:

Date:

NRC Contacts:

Code Developer:

UýS. Nuclear Regulatory CommissionOffice of Nuclear Reactor RegulationDivision of Reactor Program Management

June 25, 1997 11:00 a.m.

J. Y. Lee Phone: (301) 415 1080e-mail: [email protected]

J. J. Hayes Phone: (301) 415 3167e-mail: [email protected] .


J. V. Ramsdell Phone: (509) 372 6316e-mail: [email protected]



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


1

10.060.0

Ground-level releaseRelease 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 namestb2zzaz.logtb2zzaz.cfd

Minimum Wind Speed (m/s)Surface roughness length (m)Sector averaging constant


- .5.- .20= 4.3

.00

.00



Hours of missing dataHours direction in window .=

Hours elevated plume w/ dir. in window =

Hours of calm windsHours direction not in window or calm =

43824297

i50240

75727746

DISTRIBUTION SUMMARY DATA BY AVERAGING INTERVALAVER. PER. 1 2 4 8UPPER 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-06ABOVE 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

121.00E-021. OOE-06

0.30564.

0.12736.43300.70.59

24 96 1681.00E-02 1.OE-02 1.0oC-021.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

3601.00E-021.00E-06

0.42457.

0..0.

42457.100.00

7201. OOF-021.00E-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



02414

to

to

to

to

to

2 hours8 hours24 hours4 days30 days


5 .27E-034. 13E-031. 70E-031.21E-031. 02E-03

HOURLY VALUE RANGEMAX X/Q MIN X/Q

6.98E-03 4.78E-044.07E-03 2.79E-04


Attachment 4 to PLA-6124 EC-ENVR-1058, Revision I · Yes, Re/er to NDAP-QA-0730 and NDAP-QA-0731 El...

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Transcript of Attachment 4 to PLA-6124 EC-ENVR-1058, Revision I · Yes, Re/er to NDAP-QA-0730 and NDAP-QA-0731 El...