Text

R-1109298-01, Revision 3, Analysis of Control Room X/Q Values for Releases at Indian Point Generating Station Unit 3, Using ARCON96 Computer Code.
	ML050390517
Person / Time
Site:	Indian Point
Issue date:	01/24/2005
From:	Fenstermacher T, Lewis J; Entergy Nuclear Northeast, Entergy Nuclear Operations
To:	; Office of Nuclear Reactor Regulation
References
	NL-05-013 R-1109298-01, Rev 3
	Download: ML050390517 (51)
	v • d • e

ATTACHMENT 2 TO NL-05-013 Revised ABS Consulting Report R-1109298-01, Revision 3 dated January 24, 2005, "Analysis of Control Room X/Q Values for Releases at Indian Point Generating Station Unit Number 3 Using ARCON96 Computer Code".

(26 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

ANALYSIS OF CONTROL ROOM y/O VALUES FOR RELEASES AT THE INDIAN POINT GENERATING STATION UNIT NUMBER 3 USING THE ARCON96 COMPUTER CODE ABS CONSULTING REPORT R-1109298-01, REVISION 3 24 JANUARY 2005

JAN.24'2005 14:32 3(19212362 X1561 P. OC2/002 WABSConsufting APPROVAL COVER SHEET

Title:

Analysis of Control Room X/Q Values for Releases at the Indian Point Generating Station Unit Number 3 Using the ARCON96 Computer Code Report Number R-1 103298-01 Client: Enteray Nuclear Northeast Project, Analysis of Control Room X/Q Values for Indian Point Generating Station Unit Number 3 Revision Approval Number Date Prepared Raviowed Approved 0 £-118102 T. Edward Jci ei Jacke LewsKethWoodard et odr

____t02_ Fenstermacher 1 121402 Fenstermacher Jackie Lewis Mark Abrams 2 1/1005 Fenstermacher Jacde Lewis Keith Woodard 3 Mile'~p H~ po t@

R-1 109298-0l. R.-v. 3 Page 2 of 26 24 January 2005

TABLE OF REVISIONS Revision 0 Date: 18 September 2002 Original Issue Revision I Date: 4 December 2002 Revised to include title page, table of revisions, summary, clarify reference for ARCON96, add reference for WK2ARCON, add reference for meteorological data, clarify reference for units of meteorological data.

Revision 2 Date: 10 January 2005 Revised to replace Table 1, which had erroneous values for the coordinates for the Auxiliary Boiler Feed Building. The spelling of "Auxiliary" was corrected in several places Revision 3 Date: 24 January 2004 Revised to replace Auxiliary Boiler Feed Building fan release point with organ pipe and silencer release points. Also, corrected height and size of containment vent release.

R-1109298-01, Rev. 3 Page 3 of 26 24 January 2005

SUMMARY

The X/Q values for the meteorological dispersion between several release points and the Indian Point 3 control room intake were determined using the ARCON96 computer code. The release points considered were the containment vent, the containment surface, the side of the auxiliary boiler feed building, the auxiliary boiler feed building atmospheric dump valve silencers, and the auxiliary boiler feed building safety valve organ pipes. Release periods of 0 hours0 days 0 hours 0 weeks 0 months to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , I day to 4 days, and 4 days to 30 days were calculated. The X/Q values were highest for the auxiliary boiler feed building organ pipes, followed by the side of the auxiliary boiler feed building, the auxiliary boiler feed building silencers, and the containment vent. The X/Q values were lowest for the containment surface release.

R-I 109298-01, Rev. 3 Page 4 of 26 24 January 2005

' -I TABLE OF CONTENTS Approval Cover Sheet ...................................................... 2 Table of Revisions ...................................................... 3 Summary ...................................................... 4 Table of Contents ...................................................... 5 Introduction ...................................................... 6 Input Data ...................................................... 6 Methodology ...................................................... 8 Results ...................................................... 9 References ...................................................... 9 . ARCON96 Log Files ...................................................... I R-I 109298-01, Rev. 3 Page 5 of 26 24 January 2005

INTRODUCTION ABS Consulting engineers have used the ARCON961 computer code to analyze the X/Q values at the control room intake for releases at Unit 3 of the Indian Point Generating Station. Pacific Northwest National Laboratory developed ARCON96 for the United States Nuclear Regulatory Commission. The purpose of the code is to determine the X/Q values at receptors on or near buildings from releases on or near buildings for various averaging times. It includes corrections for building wakes, low wind speeds, elevated and vent releases, and area releases.

INPUT DATA ARCON96 requires the use of hourly meteorological data for a period of at least one year. This data must include the wind direction, wind speed, and stability class; and may optionally include wind direction and wind speed for a second meteorological instrument at another height. The meteorological data used for this analysis was collected at the Indian Point Generating Station in 1995, 1996, and 19972. ABS Consulting received the data on diskettes and a program was written to extract the data to the format required by ARCON96 3 . The wind instruments at heights of 10 m and 60 m were used. Wind speed in the unconverted data has units of miles per hour for wind speed and 'F for temperature and temperature difference measurements4 . The converted file retains the wind speed units as miles per hour, while the temperature differences are converted to stability classes A to G.

ARCON96 also requires data on the source and receptor locations, as well as other geometric data, flow data, and the initial plume dimensions. For the source, the code requires that the release be specified as a ground, vent, or stack release. If the release is well above the attached building, it is a stack release. If it is not a stack release, but is released with a large enough vertical velocity, ARCON96 treats it as a vent release. The code treats releases from the surface of the building without vertical velocity as ground releases. The model also requires the release height, building area, vertical velocity, stack flow (volumetric flow rate), and stack radius. The building area was taken to be the lateral area of the containment building. The receptor data includes the distance from the source, the direction from the source, the intake height, and the elevation difference if the source and receptor are measured from different reference planes. ARCON96 also requires the initial plume dimensions for area releases. The determination of these values will be discussed below. There are several other input values, but they did not need to be altered from their default values for this analysis.

The ARCON96 analysis for the Indian Point Nuclear Plant required calculation of XJQ values for five locations: a containment surface leak, a release from the containment vent, the side of the auxiliary boiler feed building, the auxiliary boiler feed building safety valve organ pipes, and the auxiliary boiler feed building atmospheric dump valve silencers. Instructions on determining the locations of the release points and the control room intake were taken from Letter NEA-05-002 5 . We took the information used to determine the location and size of the containment surface leak (described in the next paragraph) from U.E. & C. drawing 9321-F-131936 and the receptor location (the point on the surface closest to the control room intake was chosen). The height of the containment vent was taken from the same drawing, and the horizontal coordinates were taken from drawing C004 7 . The locations of the auxiliary boiler feed building safety valve "organ pipes" were taken from drawing 9321-F-20493 8 for the horizontal coordinates and from drawing 9321-F-20503 9 for the elevation. The location of the silencers was taken from Con Ed Drawing A210148-l'0 . The location of the intersection of the shield wall and the containment (the closest point on the auxiliary feed pump building south wall to the control room intake) was taken from drawings C004 7 and 9321-F40433-5", and the dimensions of the blowout panels from R-l 109298-01, Rev. 3 Page 6 of 26 24 January 2005

Drawing 9321-F-14853' 2 . The location of the control room intake was taken from drawing 9321-F-4017313. These values were then used to determine the distance from the source to the receptor, and with a correction from plant north to true north, for the direction to the source. The grade elevation, used to determine the height of the source and receptor locations above the ground, was taken to be the top of the paved area South and West of the containment on drawing C004 .

The ARCON96 manual states that, "Methods for determining the initial diffusion coefficients that define a virtual source involve subjective decisions." Numerical integration over the part of the surface available for release, (that is, above the adjoining buildings where present), was used to determine the effective distance and height of the containment surface release. The heights and locations of the adjoining buildings (i.e., the electrical tunnel, auxiliary feed pump building, and fan house) were taken from drawings 9321-F-1536314 and 9321-F-40433-5"1 . The initial plume standard deviations used were equal to one-sixth of the width and available height of the containment. For the release from the side of the auxiliary boiler feed, the intersection of the containment and the shield wall was the closest point to the control room intake, and was used for the release. The initial plume dimensions for that case were one sixth of the height and average width of the blowout panels on the south side of the building, projected onto a vertical plane perpendicular to the line of sight from the release point to the control room intake.

The auxiliary boiler feed building safety valve organ pipes were modeled using the closest point on the organ pipe that is closest to the control room intake, and was modeled as a point release. The auxiliary boiler feed building atmospheric dump valve silencers were modeled using the closest point on the silencer that is closest to the control room intake, and was modeled as a point release. The containment vent release was modeled at the center of the vent. The initial horizontal plume dimension for vent releases is the equivalent vent diameter divided by six. Table 1 shows the source and receptor locations, Table 2 shows the geometric input data locations, and Table 3 shows the flow and initial plume size data, and Table 4 shows miscellaneous input data.

Position, ft Location N E Elevation Containment Surface 5997.0 1475.1 150.1 Containment Vent 6023.0 1475.0 268.0 Auxiliary Boiler Feed Building Side 5991.7 1410.1 66.5 Auxiliary Boiler Feed Building Organ Pipes 5995.5 1395.6 97.0 Auxiliary Boiler Feed Building Silencers 6012.9 1390.1 133.1 Control Room Intake 5783.8 1476.0 25.5 Table 1. Source and receptor locations on plant grid.

Distance Direction to Intake to Release Release Building Receptor Height Source Type Height Area Location m m 0 Flag m m2 Containment Surface l 65.01 2.2S 38.32 1 40.25 3059.33 Containment Vent l 72.92 2.2S 38.32 1 74.91 3059.33 Auxiliary Boiler Feed Building Side 66.48 2.2S 20.98 I 14.78 3059.33 Auxiliary Boiler Feed Building Organ Pipes 68.8 2.2S 2.8 1 24.08 3059.33 Auxiliary Boiler Feed Building Silencers 73.74 2.2 18.01 1 35.1q 3059.33 Table 2. ARCON96 geometric input data.

R-1 109298-01, Rev. 3 Page 7 of 26 24 January 2005

METHODOLOGY We prepared the input data on a Microsoft Excel spreadsheet. A Visual Basic macro translated the data from the spreadsheet into input files for ARCON96, and wrote a batch file to run the cases. The batch file invoked ARCON96 to run the individual cases and produce the required output. Another Visual Basics macro read the data back into the spreadsheet. The results for the individual cases were printed and used to verify that the input and output data agreed with the values on the spreadsheet.

Initial Plume Vertical Stack Stack Dimensions Velocity Flow Radius m Location M/S m;/S m cry I CYZ Containment Surface 0.00 0.0( 0.00 7.32 13.31 Containment Vent 0.00 0.0( 0.00 0.26 0.0 Auxiliary Boiler Feed Building Side 0.00 0.0( 0.00 0.96 2.39 Auxiliary Boiler Feed Building Organ Pipes 0.00 0.0( 0.00 0.00 0.0 uxiliary Boiler Feed Building Silencers 0.00- 0 0( 0.00 0.0~ 0.0 Table 3. ARCON96 flow and plume dimension data.

Reference Information .

Grade, feet 18 North Adjustment, 0 38.5611 Wind Speed Units 2 Lower Met Height I1 Ipper Met Height 60 Roughness Length 0.1 Minimum Wind Speed. m/s 0.5 Averaging Sector Width 4 Wind Direction Window., 99 Elevation Difference 0 Table 4. ARCON96 miscellaneous data.

R-1 109298-01, Rev. 3 Page 8 of 26 24 January 2005

RESULTS Table 5 shows the results of the ARCON96 analysis. The highest values of X/Q come from the auxiliary boiler feed building safety valve organ pipes, followed by releases from the side of the auxiliary boiler feed building, auxiliary boiler feed building atmospheric dump valve silencers, the containment vent, and the containment surface.

95% X/Q from ARCON96 Oto2 ] 2to8 ( 8to24 1lto4 14to30 ID hours I hours hours days days Containment Surface 3.57E-04 3.12E-04jj 1.24E-04 1.06E-04 7.99E-05 Containment Vent 6.16E-04 5.25E-04 2.15E-04 1.79E-04 1.31E-04 Auxiliary Boiler Feed Building Side 9.86E-04 8.74E-04 4.50E-04 3.50E-04 2.80E-04 Auxiliary Boiler Feed Building Organ Pipes 1.14E-03 1.04E-03 5.05E-04 4.01E-04 3.2 1E-04 Auxiliary Boiler Feed Building Silencers 9.08E-0 8.15E-04 3.64E-04 2.892-04 2.14E-0 Table 5. Results of ARCON96 analysis.

REFERENCES

1. Atmospheric Relative Concentrations in Buildint Wakes, NUREG/CR-6331REV1, Pacific Northwest National Laboratory, Richland, WA, May 1997. (ARCON96 Manual)

2. Memorandum M-254060-01, April 5, 1999.

3. MET2ARCN Code Certification Package, CCP-Beth-04, April 11, 2000.

4. Memorandum M-254060-02, April 7, 2000.

5. Letter NEA-05-002, Floyd Gumble, Senior Lead Engineer, Entergy Nuclear Northwest to T. Edward Fenstermacher, ABS Consulting, January 20, 2005.

6. Containment Discharge Duct for Consolidated Edison Company Indian Point Generating Station Unit No. 3, U. E. & C. Drawing No. 9321-F-13193.

7. Power Authority State of New York, Indian Point Unit No. 3 - Additional Facilities, Plot Plan Sheet 2, Drawing No. C004 Revision 8.

8. Yard Area - West of Containment Building Main Steam Piping Plan Sheet No. 1, Drawing No.

9321-F-20493 Rev. 17

9. Yard Area - West of Containment Building Main Steam Piping Sections and Elevations Sheet No. 2, Drawing No. 9321-F-20503 Rev. 15

10. Flow Off Muffler Additions Main Steam Dump Valve Vent Lines Sheet No. 1, A210148-1

11. Miscellaneous Plant Areas & Buildings Ventilation Systems Plans, Sections and Details for Consolidated Edison Company Indian Point Generating Station Unit No. 3, U. E. & C. Drawing No.

9321 -F40433-5.

R-1 109298-01, Rev. 3 Page 9 of 26 24 January 2005

12. Drawing 9321-F-14853 Rev. 3

13. Indian Point Unit No. 3 Nuclear Power Plant, Control Building (El 15'-00") Air Conditioning Equipment Room Plants & Sections, New York Power Authority Drawing 932 1-F-40173 Revision 11.

14. Profile Looking North Thru Intake Structure, Turbine, Prim. Aux. Bldgs. & Waste H. T. Pit for Consolidated Edison Company Indian Point Generating Station Unit No. 3, U. E. & C. Drawing No.

9321-F-15363.

R-1 109298-01, Rev. 3 Page 10 of 26 24 January 2005

ATTACHMENT 1. ARCON96 LOG FILES Printed copies of the log files from the four ARCON96 computer code runs follow.

R-l 109298-01, Rev. 3 Page I11 of 26 24 January 2005

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 L. A Brown Phone:

e-mail:

Phone:

(301) 415 3167 jjh~nrc.gov (301) 415 1232 C

e-mail: lab2Gnrc.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 1/21/2005 at 12:14:06

- - - - ARCON INPUT Number of Meteorological Data Files = 3

(

Meteorological Data File Names C:\IP3Prime\IP_1995.MET C:\IP3Prime\IP_1996.MET C:\IP3Prime\IP_1997.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 (m) = 40.3 Building Area (m12) = 3059.3 R-1 109298-01, Rev. 3 Page 12 of 26 24 January 2005

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) 038 Wind direction sector width (deg) = 90 Wind direction window (deg) = 353 - 083 Distance to intake (m) = 65.0 Intake height (m) 2.3 Terrain elevation difference (m) = .0 Output file names ip3slrl.log ip3slrl.cfd Minimum Wind Speed (m/s) = .5 Surface roughness length (m) = .10 Sector averaging constant 4.0 Initial value of sigma y = 7.32 Initial value of sigma z = 13.31 Expanded output for code testing not selected Total number of hours of data processed = 26304 Hours of missing data 170 Hours direction in window = 8468 Hours elevated plume w/ dir. in window = 0 Hours of calm winds 361 Hours direction not in window or calm 17305 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-03 1.00E-03 1.OOE-03 1.00E-03 1.OOE-03 1.00E-03 1.00E-03 1.OOE-03 1.OOE-03 1.OOE-03 LOW LIM. 1.OOE-07 1.00E-07 1.OOE-07 1.OOE-07 1.OOE-07 1.00E-07 1.OOE-07 1.00E-07 1.OOE-07 1.00E-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 8829. 10172. 11979. 14584. 16697. 20464. 25561. 25549. 25378. 25002.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

ZERO 17305. 15946. 14109. 11444. 9351. 5547. 280. 46. 0. 0.

TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.

% NON ZERO 33.78 38.95 45.92 56.03 64.10 78.67 98.92 99.82 100.00 100.00 95th PERCENTILE X/Q VALUES 3.57E-04 3.54E-04 3.45E-04 3.23E-04 2.65E-04 1.90E-04 1.27E-04 1.07E-04 9.39E-05 8.61E-05 R-1 109298-01, Rev. 3 Page 13 of 26 24 January 2()05

95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3 . 57E-04 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3 . 12E-04 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.24E-04 1 to 4 days 1. OGE-04 4 to 30 days 7. 99E-05 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 3. 97E-04 3.53E-05 SECTOR-AVERAGE 2 .49E-04 2.21E-05 NORMAL PROGRAM COMPLETION Page 14 of 26 24 January 2005 R-1 109298-01, Rev. 3

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:

e-mail:

(301) 415 1232 lab2Gnrc.gov (

Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j-ramsdellgpnl.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 1/21/2005 at 12:14:07

- - - - ARCON INPUT Number of Meteorological Data Files = 3 Meteorological Data File Names C:\IP3Prime\IP_1995.MET

(

C:\IP3Prime\IP_1996.MET C:\IP3Prime\IP_1997.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 (m) = 74.9 Building Area (mA2) = 3059.3 Effluent vertical velocity (m/s) = .00 R-I 109298-01, Rev. 3 Page 15 of 26 24 January 2005

Vent or stack flow (mA3/s) = .00 Vent or stack radius (m) = .00 Direction .. intake to source (deg) 038 Wind direction sector width (deg) 90 Wind direction window (deg) 353 - 083 Distance to intake (m) 72.9 Intake height (m) = 2.3 Terrain elevation difference (m) = .0 Output file names ip3s2rl.log ip3s2rl.cfd

(

Minimum Wind Speed (mWs) = .5 Surface roughness length (m) = .10 Sector averaging constant 4.0 Initial value of sigma y = .26 Initial value of sigma z = .00 Expanded output for code testing not selected Total number of hours of data processed = 26304 Hours of missing data = 170 Hours direction in window = 8497 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 293 Hours direction not in window or calm = 17344 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 (

UPPER LIM. 1.OOE-03 1.OOE-03 1.OOE-03 l.OOE-03 1.OOE-03 1.OOE-03 1.OOE-03 1.OOE-03 1.OOE-03 1.OOE-03 LOW LIM. 1.OOE-07 1. OOE-07 1.00E-07 1.00E-07 1.OOE-07 1.OOE-07 1.OOE-07 1. OOE-07 1. OOE-07 1.00E-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 8790. 10124. 11924. 14514. 16620. 20376. 25539. 25549. 25378. 25002.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 46. 0. 0.

ZERO 17344. 15994. 14164. 11514. 9428. 5635. 302. 0. 0. 0.

TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.

% NON ZERO 33.63 38.76 45.71 55.76 63 .81 78.34 98.83 100.00 100.00 100.00 95th PERCENTILE X/Q VALUES 6.16E-04 6.03E-04 5.80E-04 5.48E-04 4.55E-04 3.26E-04 2.16E-04 1.82E-04 1.56E-04 1.43E-04 95% X/Q for standard averaging intervals R-l 109298-01, Rev. 3 Page 160of26 24 January 20()5

0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 6.16E-04 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 5.25E-04 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2. 15E-04 1 to 4 days 1.79E-04 4 trio 30 days 1.31E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 7.88E-04 3 .47E-05 SECTOR-AVERAGE 4.94E-04 2. 18E-05 NORMAL PROGRAM COMPLETION (

(,

R-1109298-01, Rev. 3 Page 17 of 26 24 January 2005

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:

e-mail:

(301) 415 1232 lab2Qnrc.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 1/21/2005 at 12:14:07

- - - - ARCON INPUT

Number of Meteorological Data Files Meteorological Data File Names C:\IP3Prime\IP_1995.MET

= 3

(

C:\IP3Prime\IP_1996.MET C:\IP3Prime\IP._1997.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 (m) = 14.8 Building Area (m^2) = 3059.3 Effluent vertical velocity (mis) = .00 R-1 109298-01, Rev. 3 Page IS of 26 24 January 2005

Vent or stack flow (m^3/s) = .00 Vent or stack radius (m) = .00 Direction .. intake to source (deg) 021 Wind direction sector width (deg) = 90 Wind direction window (deg) 336 - 066 Distance to intake (m) 66.5 Intake height (m) 2.3 Terrain elevation difference (m) _ .0 Output file names ip3s3rl.log ip3s3rl.cfd Minimum Wind Speed (mWs) = .5 Surface roughness length (m) = .10 Sector averaging constant 4.0 Initial value of sigma y = .96 Initial value of sigma z 2.39 Expanded output for code testing not selected Total number of hours of data processed = 26304 Hours of missing data 170 Hours direction in window = 10861 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 284 Hours direction not in window or calm = 14989 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL 4

AVER. PER.

UPPER LIM.

LOW LIM.

1.OOE-02 1.OOE-06 1

1.OOE-02 1.OOE-06 2

1.OOE-02 1.OOE-06 1.00E-02 1.00E-06 8 12 1.0OE-02 1.00E-06 24 1.00E-02 1.OOE-06 96 1.00E-02

1. OOE-06 168 1.OOE-02 1.OOE-06 360 1.OOE-02 1.00E-06 720 1.00E-02 1.OOE-06

(

ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 11145. 12697. 14733. 17551. 19624. 22947. 25829. 25595. 25378. 25002.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

ZERO 14989. 13421. 11355. 8477. 6424. 3064. 12. 0. 0. 0.

TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.

% NON ZERO 42.65 48.61 56.47 67.43 75.34 88.22 99.95 100.00 100.00 100.00 95th PERCENTILE X/Q VALUES 9.86E-04 9.62E-04 9.38E-04 9.02E-04 7.75E-04 6.01E-04 4.12E-04 3.58E-04 3.23E-04 2.98E-04 95% X/Q for standard averaging intervals R-1 109298-01, Rev. 3 Page 19 of 26 24 January 20()5

0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 9.86E-04 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8.74E-04 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4. 50E-04 1 to 4 days 3.50E-04 4 to 30 days 2.80E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 1.38E-03 1.95E-04

SECTOR-AVERAGE 8.62E-04 1.22E-04 NORMAL PROGRAM COMPLETIC )N

(

R-1 109298-01, Rev. 3 Page 20 of 26 24 January 2005

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:

e-mail:

(301) 415 1232 lab2@nrc.gov

(

Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: j-ramsdellcpnl.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 1/21/2005 at 12:14:07 ARCON INPUT Number of Meteorological Data Files = 3 Meteorological Data File Names C:\IP3Prime\IP_1995.MET C:\IP3Prime\IP_1996.MET C:\IP3Prime\IP_1997.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 (m) = 24.1 Building Area (m'2) 3059.3 Effluent vertical velocity (m/s) a .00 R-1 109298-01, Rev. 3 Page 21 of 26 24 January 2005

Vent or stack flow (m'3/s) = .00 Vent or stack radius (m) = .00 Direction .. intake to source (deg) = 018 Wind direction sector width (deg) = 90 Wind direction window (deg) = 333 - 063 Distance to intake Cm) 68.9 Intake height (m) = 2.3 Terrain elevation difference (m) = .0 Output file names ip3s4rl.log ip3s4rl.cfd Minimum Wind Speed (m/s) = .5 Surface roughness length (m) = .10 Sector averaging constant 4.0 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 = 26304 Hours of missing data = 170 Hours direction in window = 10871 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 284 Hours direction not in window or calm = 14979 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 (

UPPER LIM. 1.00E-02 1.00E-02 1.OOE-02 l.OOE-02 1.OOE-02 1.00E-02 1.OOE-02 1.OOE-02 1.OOE-02 1.00E-02 \

LOW LIM. 1.00E-06 1.OOE-06 1.OOE-06 1.00E-06 1.OOE-06 1.OOE-06 1.OOE-06 1.00E-06 1.00E-06 1.00E-06 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 11155. 12764. 14857. 17704. 19764. 23061. 25829. 25595. 25378. 25002.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

ZERO 14979. 13354. 11231. 8324. 6284. 2950. 12. 0. 0. 0.

TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 25841. 25595. 25378. 25002.

% NON ZERO 42.68 48.87 56.95 68.02 75.88 88.66 99.95 100.00 100.00 100.00 95th PERCENTILE X/Q VALUES 1.14E-03 l.l1E-03 1.09E-03 1.06E-03 9.OOE-04 6.91E-04 4.73E-04 4.12E-04 3.69E-04 3.41E-04 95% X/Q for standard averaging intervals R-1 109298-01, Rev. 3 Page 22 of 26 24 January 2005

0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1. 14E-03 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.04E-03 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.05E-04 1 to 4 days 4.01E-04 4 to 30 days 3.21E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 1.55E-03 1.97E-04 SECTOR-AVERAGE 9.74E-04 1.24E-04 NORMAL PROGRAM COMPLETIC)N (a

R-1 109298-O1, Rev. 3 Page 23 of 26 24 January 2005

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:

e-mail:

(301) 415 1232 lab2Gnrc.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 1/21/2005 at 12:14:07

- - - - ARCON INPUT

Number of Meteorological Data Files Meteorological Data File Names

- 3

(

C:\IP3Prime\IP-1995.MET C:\IP3Prime\IPl996.MET C:\IP3Prime\IPl997.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 (m) = 35.1 Building Area (m^2) = 3059.3 Effluent vertical velocity (mis) = .00 R-1 109298-01, Rev. 3 Page 24 of 26 24 January 2005

Vent or stack flow (m'3/s) = .00 Vent or stack radius Cm) = .00 Direction .. intake to source (deg) = 018 Wind direction sector width (deg) = 90 Wind direction window (deg) = 333 - 063 Distance to intake (m) = 73.8 Intake height (m) = 2.3 Terrain elevation difference (m) = .0 Output file names ip3s5rl.log ip3sSrl.cfd (

Minimum Wind Speed (mWs) = .5 Surface roughness length (m) - .10 Sector averaging constant = 4.0 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 = 26304 Hours of missing data = 170 Hours direction in window = 9586 Hours elevated plume w/ dir. in window = 0 Hours of calm winds = 401 Hours direction not in window or calm = 16147 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720(

UPPER LIM. 1. OOE-02 1.00E-02 1.OOE-02 1.OOE-02 1. OOE-02 1. OOE-02 1.OOE-02 1. OOE-02 1.00E-02 1. OE-02 LOW LIM. 1. OOE-06 1.OOE-06 1.OOE-06 1.OOE-06 1.OOE-06 1. OOE-06 1.OOE-06 1.OOE-06 1.00E-06 1.00E-06 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 9987. 11386. 13333. 16118. 18258. 21911. 25747. 25595. 25378. 25002.

BELOW RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

ZERO 16147. 14732. 12755. 9910. 7790. 4100. 94. 0. 0. 0.

TOTAL X/Qs 26134. 26118. 26088. 26028. 26048. 26011. 2584 1. 25595. 25378. 25002.

% NON ZERO 38.21 43.59 51.11 61.93 70.09 84.24 99.64 100.00 100.00 100.00 95th PERCENTILE X/Q VALUES 9.08E-04 8.99E-04 8.80E-04 8.38E-04 7.OOE-04 5.22E-04 3.47E-04 2.96E-04 2.58E-04 2.32E-04 95% X/Q for standard averaging intervals R-1 109298-01, Rev. 3 Page 25 of 26 24 January 2005

0 to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 9. 08E-04 2 to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 8. 15E-04 8 to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 3. 64E-04 1 to 4 days 2. 89E-04 4 to 30 days 2. 14E-04 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 1.24E-03 6.83E-05 SECTOR-AVERAGE 7.79E-04 4.28E-05 NORMAL PROGRAM COMPLETION (

(

R-1 109298-01, Rev. 3 Page 26 of 26 24 January 2005

ATTACHMENT 3 TO NL-05-013 ERRATA PAGES FOR INDIAN POINT NUCLEAR GENERATING UNIT 3 ALTERNATE SOURCE TERM June 2, 2004 Submiftal (Summary Table and 10 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

Errata List for IP3 AST LR EA.iBowvs > N An u ICEv 50 Table 12 Added footnote to discuss evaluation of corrections to X/Q inputs 53 Table 14 Added footnote to discuss evaluation of corrections to X/Q inputs 56 Table 17 Added footnote to discuss evaluation of corrections to X/Q inputs 59 Table 18 Added footnote to discuss evaluation of corrections to X/Q inputs 61 Table 19 Added footnote to discuss evaluation of corrections to X/Q inputs 64 Table 20 Added footnote to discuss evaluation of corrections to X/Q inputs 65 Table 21 Added footnote to discuss evaluation of corrections to X/Q inputs 66 Table 22 Added footnote to discuss evaluation of corrections to 6/Q inputs 67 Table 23 Added footnote to discuss evaluation of corrections to X/Q inputs 68 Table 24 Added footnote to discuss evaluation of corrections to X/Q inputs Errata List for IP3 AST Rpt 1-26-05 (2).doc

Table 12 (Cont.): Assumptions Used for Large Break LOCA Dose Analysis Containment spray DF Elemental 200 Particulate 1000 Credited containment sump volume 374,400 gal Leakage of sump solution outside of containment 0 - 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 1.0 gph 4- 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 0.0 gph

> 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months 4.0 gph Iodine airborne fraction for leakage of sump solution outside of containment 0 - 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 10.0%/0 4- 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months NA 2.7%

> 6.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months Control Room atmospheric dispersion (X/Q) factors Releases from containment surface"'):

0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.57E4 sec/in 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.12E-4 sec/m 3 8- 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.24E-4 sec/n 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.06E-4 sec/n 3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 7.99E-5 sec/rn3 Control Room atmospheric dispersion (X/Q) factors Releases from containment vent 2 )(3: I 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/m 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.92E-4 sec/m3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2.06E-4 sec/r 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.69E-4 sec/n 3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 1.26E-4 sec/m 3 Notes:

1. Used for activity released via containment leakage

2. Used for activity released via leakage of sump solution outside of containment (RCP seal leak-off and ECCS) 3 Subsequent to submittal of the original version of this report, the X/Q values were corrected from the original determination. The revised values are sightly higher than those used in the dose analysis:

0- 2 hr 6.16E-4 sec/in3 2- 8 hr 5.25E-4 sec/c 8- 24 hr 2.15E-4 sec/n 24- 96 hr 1.79E-4 sec/n 3 96 - 720 hr 1.31 E-4 sec/m3 Evaluation of the LBLOCA dose analysis has determined that, duc to unspecified conservatisms in the analysis, the reported doses do not change.

Page 50 of 69 Errata I

Table 14 (Cont.): Assumptions Used for SGTR Dose Analysis Activity Release Data Ruptured steam generator Rupture flow See Table 13 Flashed rupture flow See Table 13 Steam releases See Table 13 Intact steam generators Primary to secondary leakage 0.3 gpm/SG Steam releases See Table 13 Iodine partition factor Condenser 0.01 SG 0.01 except for flashed break flow Control Room atmospheric dispersion (X/Q) factors Secondary releases('):

0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/m 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/in 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/m 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/rr3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/n 3 Note:

1. Subsequent to submittal of the original version of this report, the X/Q values were corrected from the original determination. The revised values arc lower than those used in the dose analysis. Therefore, the reported doses arc bounding and have not been revised.

Page 53 of 69 Errata I

Table 17 (Cont.): Assumptions Used for Locked Rotor Dose Analysis Release Modeling Cont.

Secondary side mass 3.193E7 gm/SG Control Room atmospheric Dispersion (X/Q)

Factors Secondary releases('): I 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/n 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/n 3 8- 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/n 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/n 3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/n 3 Note:

I Subsequent to submittal of the original version of this report, the X/Q values wvere corrected from the original determination. The revised values are lower than those used in the dose analysis. Therefonr, the reported doses are bounding and have not been revised.

Page 56 of 69 Errata I

Table 18 (Cont.): Assumptions Used for Rod Ejection Dose Analysis Secondary side mass 3.193E7 gmppSGt Control Room Atmospheric Dispersion Factors Control Room atmospheric dispersion (X/Q) factors Releases from containment surfacet '):

0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.57E-4 sec/in 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.12E-4 sec/ir 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.24E-4 sec/rr3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.06E4 sec/in 3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 7.99E-5 sec/n 3 Control Room atmospheric dispersion (X/Q) factors Secondary releases (2) (3) 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/in 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/n 3 8- 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/in 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/n 3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/rr3 Notes:

1. Used for activity released via containment leakage.

2. Used for activity released via secondary releases.

3 Subsequent to submittal of the original version of this report, the X/Q values were corrected from the original determination. The revised values are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

Page 59 of 69 Errata I

I - -- -

Table 19 (Cont.): Assumptions Used for Steam Line Break Dose Analysis SG iodine water/steam partition coefficient Faulted SG 1.0 Intact SGs 0.01 RCS mass 1.960E8 gm Initial intact SG mass 3.193E7 gm/SG Control Room atmospheric dispersion (X/Q) factors Intact SG releases('): I 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/n 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/n 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/rn3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/m3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/i 3 Control Room atmospheric dispersion (X/Q) factors Faulted SG releases('): I 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.18E-3 sec/n 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.06E-3 sec/n 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.42E4 sec/n 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.09E-4 sec/n 3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.27E-4 sec/rr3 Note:

I Subsequent to submittal of the original version of this report, the X/Q values were corrected from the original determination. The revised values arc lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

Page 61 of 69 Errata I

Table 20 (Cont.): Assumptions Used for Small Break LOCA Dose Analysis Secondary Side mass pr3.193E7 gm/SG Control Room Atmospheric Dispersion Factors Control Room atmospheric dispersion (X/Q) factors Releases from containment surface('):

0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.57E-4 sec/rn3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.12E-4 sec/n 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.24E-4 sec/rn3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.06E-4 sec/rn3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 7.99E-5 sec/n 3 Control Room atmospheric dispersion (X/Q) factors Secondary releases (2) (3) I 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/n 3 2- 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/rn3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/r 3 24- 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/n 3 96- 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/rn3 Notes:

1. Used for activity released via containment leakage.

2. Used for activity released via secondary releases.

3 Subsequent to submittal of the original version of this report, the X/Q values were corrected from the original determination. The revised values are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

Page 64 of 69 Errata I

Table 21: Assumptions Used for Gas Decay Tank Rupture Dose Analysis Gas decay tank inventory 50,000 Ci of dose equivalent Xe-1 33 Duration of release 5 minutes Control Room atmospheric dispersion (X/Q) factors Releases from containment vent('): I 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/ni 3 Note:

I Subsequent to submittal of the original version of this report, the X/Q value was corrected from the original determination. The revised value increased slightly to 6.1 6E4 sec/m 3 .

Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

Page 65 of 69 Errata I

Table 22: Assumptions Used for Volume Control Tank Rupture Dose Analysis Volume control tank inventory (Ci)

I-130 1.97E-2 1-131 6.29E- 1 1-132 9.61E-I 1-133 1.14E0 1-134 2.33E-1 1-135 7.38E-1 Kr-85m 1.61 E2 Kr-85 2.24E2 Kr-87 4.96EI Kr-88 2.40E2 Xe-131m 3.95E2 Xe-133m 4.18E2 Xe- 133 3.04E4 Xe- 135m 7.54EI Xe- 135 9.57E2 Xe-138 6.68E0 Reactor coolant iodine activity prior to accident 1.0 gCi/gm of DE 1-131 - See Table 15 Reactor coolant noble gas activity prior to accident 1.0% fuel defect level - See Table 6 Iodine partition factor in VCT 0.01 Duration of release of VCT contents 5 minutes Letdown flow rate 132 gpm Operator action time to isolate the letdown line 30 minutes Letdown line demineralizer iodine DF 10 Airborne fraction for iodine in water released from 0.1 letdown line Control Room atmospheric dispersion (X/Q) factors Releases from containment vente:

0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.9313-4 sec/n 3 Note:

I Subsequent to submittal of the original version of this report, the X/Q value was corrected 3

from the original determination. The revised value increased slightly to 6.16E4 sec/m3 .

Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

Page 66 of 69 Errata I

Table 23: Assumptions Used for Holdup Tank Failure Dose Analysis Holdup tank volume 8500 ft3 Holdup tank full level 80%

Reactor coolant iodine activity prior to accident 1.0 gCi/gm of DE 1-131 - See Table 15 Reactor coolant noble gas activity prior to accident 1.0% fuel defect level - See Table 6 Letdown line demineralizer iodine DF 10 Time assumed to fill holdup tank 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Iodine partition coefficient for holdup tank liquid 0.01 Duration of release 5 minutes Control Room atmospheric dispersion (X/Q) factors Releases from containment vent(): I 0- 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/rn3 Note:

I Subsequent to submittal of the original version of this report, the X/Q value was corrected 3

from the original determination. The revised value increased slightly to 6.16E-4 sec/M3 .

Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

Page 67 of 69 Errata I

Table 24: Assumptions Used for FIIA Analysis Source Term Core Total Fission Product Activity (84 hrs decay) See Table 25 Number of Fuel Assemblies 193 Radial Peaking Factor 1.70 Fuel Rod Gap Fraction 1-131 12%

Kr-85 30%

Other lodines and Noble Gases 10%

Fuel Damaged One assembly Time after Shutdown 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months Water Depth 23 feet Overall Iodine Scrubbing Factor 200 Noble Gases Scrubbing Factor I Filter Efficiency No filtration of releases assumed Isolation of Release No isolation of releases assumed Time to Release All Activity 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Time to Start Crediting Emergency Control Room HVAC 24 minutes Control Room Atmospheric Dispersion (X/Q) Factor Containment Vent('):

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/rn3 Note:

I Subsequent to submittal of the original version of this report, the X/Q value was corrected from the original determination. The revised value increased slightly to 6.16E-4 sec/Mr3 .

Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

Page 68 of 69 Errata I

ATTACHMENT 5 TO NL-05-013 ERRATA PAGES FOR WCAP-1 621 2-NP INDIAN POINT NUCLEAR GENERATING UNIT 3 STRETCH POWER UPRATE NSSS AND BOP LICENSING REPORT June 3, 2004 Submittal (Summary Table and 10 Pages)

ENTERGY NUCLEAR OPERATIONS, INC.

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-286

Errata List for IP3 LR Section Page - -:LocatibnlfRevislonL - IRevislon 6.11 6.11-81 Table 6.11-17 Added footnote to discuss evaluation of corrections to X/Q inputs 6.11 6.11-83 Table 6.11-18 Added footnote to discuss evaluation of corrections to x/Q inputs 6.11 6.11-85 Table 6.11-19 Added footnote to discuss evaluation of corrections to

._X/Q inputs 6.11 6.11-87 Table 6.11-20 Added footnote to discuss evaluation of corrections to x'Q inputs 6.11 6.11-89 Table 6.11-21 Added footnote to discuss evaluation of corrections to X/Q inputs 6.11 6.11-92 Table 6.11-22 Added footnote to discuss evaluation of corrections to X/Q inputs 6.11 6.11-93 Table 6.11-23 Added footnote to discuss evaluation of corrections to

._X/Q inputs 6.11 6.11-94 Table 6.11-24 Added footnote to discuss evaluation of corrections to X/Q inputs 6.11 6.11-95 Table 6.11-25 Added footnote to discuss evaluation of corrections to X/Q inputs 6.11 6.11-96 Table 6.11-26 Added footnote to discuss evaluation of corrections to X/Q inputs Errata List for IP3 LR Sec6_11 1-26-05.doc

Table 6.11-17 (Cont.)

Assumptions Used for Steamline Break Dose Analysis Intact Steam Generator Secondary Mass 70,400 Ibm/SG Faulted Steam Generator Secondary Mass 142,400 Ibm Offslte Atmospheric Dispersion Factors See Table 6.11 -11 Offsite Breathing Rates See Table 6.11 -11 Control Room Model See Table 6.11-12 Time to Start Crediting Emergency Control Room HVAC 1 minute Control Room Atmospheric Dispersion (X/Q) Factorsl Intact SG Releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/M 3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/M 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/mr3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/r 3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/m 3 Faulted SG Releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.18E-3 sec/M 3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.06E-3 sec/mi3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.42E-4 sec/iM3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.09E-4 sec/M 3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.27E-4 sec/m 3

1. The X/Q values listed in this table are those used In the analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the X/Q values were corrected from the original determination. The revised values are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

6389\sec6_11.doc(060204) 6.11 -81 WCAP-16212-NP NSSS and BOP Licensing Report Rev. 0-errata

Table 6.11-18 (Cont.)

Assumptions Used for Locked Rotor Dose Analysis Offsite Atmospheric Dispersion Factors See Table 6.11-11I Offsite Breathing Rates See Table 6.1 1-II Control Room Model See Table 6.11-12 Time to Start Crediting Emergency Control Room HVAC 32 minutes Control Room Atmospheric Dispersion (X/Q) Factors1I Secondary Releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/mr3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/mr3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/M 3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/mr3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/M 3

1. The y/Q values listed In this table are those used in the analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the X/Q values were corrected from the original determination. The revised values are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

6389\sec6_1 .doc(060204) 6.11 -83 WCAP-16212-NP NSSS and BOP Licensing Report Rev. 0-errata

Table 6.11-19 (Cont.)

Assumptions Used for Rod Ejection Accident Steam Generator Steaming Release Path Primary Coolant Mass 1.96E8 gm Secondary Coolant Mass 1.277E8 gm (total)

Primary-to-Secondary Leak Rate 1440 gal/day Duration of Primary-to-Secondary Leakage 1 hr Steam Released from the Secondary Side 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 405,000 Ibm

> 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0 Ibm Iodine Chemical Form after Release to Atmosphere 97% elemental, 3% organic SG Iodine Steam/Water Partition Coefficient 0.01 SG Alkali Metal Steam/Water Partition Coefficient 0.001 Offsite Atmospheric Dispersion Factors See Table 6.11-11 Offsite Breathing Rates See Table 6.11 -11 Control Room Model See Table 6.11-12 Time to Start Crediting Emergency Control Room 140 seconds HVAC Control Room Atmospheric Dispersion (X/Q) Factors1 Secondary Releases:

0 -2 hours :-1.19E-3 sec/m 3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/m 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/mi3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/M 3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/M 3 Containment Releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.57E-4 sec/M 3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.12E-4 sec/M 3 8-24 hours 1.24E-4 sec/r 3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.06E-4 sec/mi3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 7.99E-5 sec/rM3

1. The XIQ values listed in this table are those used Inthe analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the XIQ values were corrected from the original determination. The values for containment leakage releases did not change and the revised values for the secondary side releases are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

I6389\sec6 I1.doc(0602041

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Table 6.11-20 (Cont.)

Assumptions Used for SGTR Dose Analysis Control Room Atmospheric Dispersion (XIQ) Factors' Secondary releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/M 3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/M 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/m3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/m3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/mr3

1. The XIQ values listed in this table are those used in the analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the XIQ values were corrected from the original determination. The revised values are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

6389\sec6j1 1.doc(060204) 6.11 -87 WCAPI16212-NP NSSS and BOP Licensing Report Rev. 0-errata

Table 6.11-21 (Cont.)

Assumptions Used for SBLOCA Analysis Steam Generator Steaming Release Path Primary Coolant Mass 1.96E8 gm Secondary Coolant Mass '1.277E8 gm (total)

Primary-to-Secondary Leak Rate 1440 gal/day total Duration of Primary-to-Secondary Leakage 1 hr Steam Released from the Secondary Side 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 405,000 Ibm

> 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 0 Ibm Steam Generator Iodine Steam/Water Partition Coefficient 0.01 Steam Generator Alkali Metal Steam/Water Partition Coefficient 0.001 Iodine Chemical Form after Release to Atmosphere 97% elemental, 3% organic Offsite Atmospheric Dispersion Factors See Table 6.11 -11 Offsite Breathing Rates See Table 6.11-11 Control Room Model See Table 6.11-12 Time to Start Crediting Emergency Control Room HVAC 140 seconds 1

Control Room Atmospheric Dispersion (X/Q) Factors Secondary Releases:

3 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 1.19E-3 sec/r 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 1.12E-3 sec/M 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 5.59E-4 sec/rM3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 4.27E-4 sec/M 3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 3.35E-4 sec/M 3 Containment Releases:

0 -2 hours 3.57E-4 sec/m3 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.12E-4 sec/M 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.24E-4 sec/M 3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.06E-4 sec/M 3 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 7.99E-5 sec/m3

1. The X/Q values listed in this table are those used in the analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the X/Q values were corrected from the original determination. The values for containment leakage releases did not change and the revised values for the secondary side releases are lower than those used in the dose analysis. Therefore, the reported doses are bounding and have not been revised.

6389\sec6_11l.doc(060204) 6.11 -89 WCAP-16212-NP NSSS and BOP Licensing Report Rev. 0-errata

Table 6.11-22 (Cont.)

Assumptions Used for LBLOCA Analysis Offsite Atmospheric Dispersion Factors See Table 6.11-11 Offsite Breathing Rates See Table 6.11 -11 Control Room Model See Table 6.11-12 Time to Start Crediting Emergency Control Room HVAC 1 minute Control Room Atmospheric Dispersion (X/Q) Factors' Containment Releases:

3 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 3.57E-4 sec/r 2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 3.12E-4 seclM 3 8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 1.24E-4 sec/M 3 24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.06E-4 sec/M 3 3

96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 7.99E-5 sec/r ECCS leakage:

3 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/r 3

2 - 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 4.92E-4 sec/r 3

8 - 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 2.06E-4 sec/r 3

24 - 96 hours0.00111 days 0.0267 hours 1.587302e-4 weeks 3.6528e-5 months 1.69E-4 sec/r 96 - 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months 1.26E-4 sec/rm3

1. The X/Q values listed In this table are those used In the analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the x/Q values were corrected from the original determination. The values for containment leakage releases did not change. The revised values for the ECCS leakage releases via the containment vent are slightly higher than those used In the dose analysis:

0 - 2 hr 6.16E-4 secm 3 2 - 8 hr 5.25E-4 sec/m 3 8-24 hr 2.15E-4sec/m 3 24 - 96 hr 1.79E-4 seCm 3 96-720 hr 1.31E-4sec/m 3 Evaluation of the LBLOCA dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

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Table 6.11-23 Assumptions Used for GDT Rupture Dose Analysis Nuclide Parameters See Table 6.1 1-10 GDT Inventory (Dose Equivalent Xe-133) 50,000 Ci Duration of Release 5 minutes Offsite Atmospheric Dispersion Factors See Table 6.1 1-11 Offsite Breathing Rates See Table 6.1 1-11 Control Room Model See Table 6.11-12 Control Room Atmospheric Dispersion (X/Q) factors' I Containment Vent Releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/m 3 Time to Start Crediting Emergency Control Room HVAC 5 minutes

1. The X/Q value listed Inthis table was used Inthe analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the X/Q values were corrected from the original determination. The revised value for the containment vent releases increased slightly to 6.1 6E-4 sec/M 3. Evaluation of the dose analysis has determined that, due to unspecified conservatisms Inthe analysis, the reported doses do not change.

I-6389\sec6_1 I .doc(060204)6 6.11 -93 WCAPL16212-NP NSSS and BOP Licensing Report Rev. 0-errata

Table 6.11-24 Assumptions Used for VCT Rupture Dose Analysis Nuclide Parameters See Table 6.1 1-1 1 VCT Inventory (Ci) See Table 6.11-6 Duration of Activity Release from Tank 5 minutes Iodine Partition Coefficient for VCT Liquid 0.01 Primary Coolant Noble Gas Activity 1.0% fuel defect level (See Table 6.11-14)

Primary Coolant Initial Iodine Activity 1.0 [tCi/gm of DE 1-131 (See Table 6.11-15)

Letdown Flow Rate 132 gpm Iodine Partition Coefficient for Letdown Releases 0.1 Letdown Line Demineralizer DF for Iodine 10 Time to Isolate Letdown Flow 30 minutes Offsite Atmospheric Dispersion Factors See Table 6.11-11 Offsite Breathing Rate See Table 6.11-11 Control Room Model See Table 6.11-12 Control Room Atmospheric Dispersion (X/Q) factors' I Containment Vent Releases:

II 0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/M 3 Time to Start Crediting Emergency Control Room HVAC 5 minutes

1. The XIQ value listed Inthis table was used Inthe analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the XIQ values were corrected from the oripinal determination. The revised value for the containment vent releases increased slightly to 6.1 6E-4 secdm .

Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

J.

6389\sec6_ 1.doc(060204) II.6.11 -94 WCAP-16212-NP NSSS and BOP Licensing Report Rev. 0-errata

Table 6.11-25 Assumptions Used for HT Failure Dose'Analysis Nuclide Parameters See Table 6.1 1-10 Duration of Activity Release from Tank 5 minutes Iodine Partition Coefficient for HT Liquid 0.01 HT Volume 8500 ft3 HT Full Level 80%

Primary Coolant Noble Gas Activity 1.0% fuel defect level (See Table 6.11-14)

Primary Coolant Initial Iodine Activity 1.0 piCi/gm of DE 1-131 (See Table 6.11-15)

Tank Fill Time 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months Letdown Demineralizer DF for lodines 10 Offsite Atmospheric Dispersion Factors See Table 6.1 1-11 Offsite Breathing Rates See Table 6.11-11 Control Room Model See Table 6.11-12 Control Room Atmospheric Dispersion (X/Q) factors' I1 Containment Vent Releases:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5.93E-4 sec/M 3 Time to Start Crediting Emergency Control Room HVAC 5 minutes

1. The XIQ value listed in this table was used Inthe analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the X/Q values were corrected from the ori 3qinal determination. The revised value for the containment vent releases increased slightly to 6.1 6E-4 sec/im Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

6389\sec6_1 1.doc(060204) 6.11-95 WCAP-16212-NP NSSS and BOP Ucensing Report Rev. O-errata

Table 6.11-26 Assumptions Used for FHA Analysis Source Term Nuclide Parameters See Table 6.11-10 Core Total Fission Product Activity (with 84 Hours Decay) See Table 6.11-27 Number of Fuel Assemblies 193 Radial Peaking Factor 1.70 Fuel Rod Gap Fraction 1-131 12%

Kr-85 30%

Other lodines and Noble Gases 10%

Fuel Damaged One assembly Time after Shutdown 84 hours9.722222e-4 days 0.0233 hours 1.388889e-4 weeks 3.1962e-5 months Water Depth 23 feet Overall Iodine Scrubbing Factor 200 Noble Gases Scrubbing Factor 1 Filter Efficiency No filtration of releases assumed Isolation of Release No isolation of releases assumed Time to Release All Activity 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Offsite Atmospheric Dispersion Factors See Table 6.1 1-11 Offsite Breathing Rates - See Table 6.1 1-11 Control Room Model See Table 6.11-12 Time to Start Crediting Emergency Control Room HVAC 24 minutes Control Room Atmospheric Dispersion (X/Q) Factors' Containment Vent:

0 - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 5:93E-4 sec/i 3

1. The X/Q value listed in this table was used In the analysis to calculate the control room operator doses for this postulated event. Subsequent to submittal of this report, the XQ values were corrected from the original determination. The revised value for the containment vent releases increased slightly to 6.1 6E-4 sec/rm3 . Evaluation of the dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

6389\sec6_1 I .doc(060204) 6.11 -96 WCAPL16212-NP NSSS and BOP Licensing Report Rev. 0-errata

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