ML050550221

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Updated Errata Pages for WCAP-16212-NP
ML050550221
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 02/11/2005
From:
Westinghouse
To:
Office of Nuclear Reactor Regulation
References
WCAP-16212-NP
Download: ML050550221 (38)
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Text

ATTACHMENT 5 TO NL-05-020 UPDATED ERRATA PAGES FOR IP3 SPU; WCAP-16212-NP Section Page Revision Location Revision Description 6.11 6.11-92 Table 6.11-22 Changed footnote to revise X/Q inputs 6.11 6.11-93 Table 6.11-23 Changed footnote to revise X/Q inputs 6.11 6.11-94 Table 6.11-24 Changed footnote to revise X/Q inputs 6.11 6.11-95 Table 6.11-25 Changed footnote to revise X/Q inputs 6.11 6.11-96 Table 6.11-26 Changed footnote to revise X/Q inputs These five updated errata pages replace the corresponding five errata pages transmitted by Entergy letter NL-05-013, Attachment 5, dated January 28, 2005.

ENTERGY NUCLEAR OPERATIONS, INC.

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

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) Factors1 Containment Releases:

0- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3.57E-4 sec/mr3 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 3.12E-4 sec/iM3 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 1.24E-4 sec/M3 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 1.06E-4 sec/m3 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 7.99E-5 sec/mi3 ECCS leakage:

0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/iM3 2 - 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.92E-4 sec/rm3 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.06E-4 sec/mi3 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 1.69E-4 sec/mr3 96 - 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 1.26E-4 sec/i 3

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. 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.OOE-4sec/m 3 2 - 8 hr 520E-4 sec/m3 8-24 hr 2.12E-4seclm 3 24 -96 hr 1.76E-4sec/m3 96-720 hr 1.30E-4sec/m3 Evaluation of the LBLOCA dose analysis has determined that, due to unspecified conservatisms in the analysis, the reported doses do not change.

3389\sec6.11.doc(060204) 6.11-92 WCAR16212-NP NSSS and BOP Ucensing RepoiIt Rev. O-updated errata I

Table 6.11-23 Assumptions Used for GDT Rupture Dose Analysis Nuclide Parameters See Table 6.11-10 GDT Inventory (Dose Equivalent Xe-133) 50,000 Ci Duration of Release 5 minutes 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 Control Room Atmospheric Dispersion (XIQ) factors' Containment Vent Releases:

0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/mi3 Time to Start Crediting Emergency Control Room HVAC 5 minutes

1. The X10 value listed inthis table was us ed 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 original3 determination. The revised value for the containment vent releases increased slightly to 6.OE-4 sec/m . Evaluation of the dose analysis has determined that, due to unspecified conservatisms inthe analysis, the reported doses do not change.

6389\sec6_1 1.doc(060204) 6.11 -93 WCAR16212-NP NSSS and BOP Ucensing Report Rev. 0-updated errata I

Table 6.11-24 Assumptions Used for VCT Rupture Dose Analysis Nuclide Parameters See Table 6.11-11 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 liCi/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 6.1 1-11 Control Room Model See Table 6.11-12 Control Room Atmospheric Dispersion WQ) factors' Containment Vent Releases:

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

1. The X/Q 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 oriPinal determination. The revised value forthe containmentventreleases increased slightlyto6.OOE-4 sec/m ... l Evaluation of the dose analysis has determined that, due to unspecified conservatisms inthe analysis, the reported doses do not change.

E;389\sec6_l 1.doc(060204) 6.11-94 WCAP.1 6212-NP NSSS and BOP Ucensina Renort Rev. 0-updated errata I

Table 6.11-25 Assumptions Used for HT Failure Dose Analysis Nuclide Parameters See Table 6.11-10 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 pCi/gm of DE 1-131 (See Table 6.11-15)

Tank Fill Time 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Letdown Demineralizer DF for lodines 10 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 Control Room Atmospheric Dispersion (X/Q) factors' Containment Vent Releases:

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

1. The 7IO 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 original determination. The revised value for the containment vent releases increased slightly to 6.OOE-4 sec/m .

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

5389\sec611 .doc(060204) 6.11-95 WCAP.16212-NP NSSS and BOP Ucensina Rewoc Rev. O-updated 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 <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Offsite Atmospheric Dispersion Factors See Table 6.11-11 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 WQ) Factors' Containment Vent:

0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/im3

1. The X/Q 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 xIQ values were corrected from the original determination. The revised value for the containment vent releases increased slightly to 6.OOE-4 sec/Mi . Evaluation of the dose analysis has determined that, due to unspecified conservatisms In the analysis, the reported doses do not change.

6389\sec6 1l.doc(060204) 6.11-96 WCAR16212-NP NSSS and BOP Ucensina Report Rev. 0-updated errata I

ATTACHMENT 6 TO NL-05-020 UPDATED ERRATA PAGES FOR IP3 AST Page Revision Location Revision Description 50 Table 12 Changed footnote to revise X/Q inputs 65 Table 21 Changed footnote to revise X/Q inputs 66 Table 22 Changed footnote to revise X/Q inputs 67 Table 23 Changed footnote to revise X/Q inputs 68 Table 24 Changed footnote to revise X/Q inputs These five updated errata pages replace the corresponding five errata pages transmitted by Entergy letter NL-05-013, Attachment 3, dated January 28, 2005.

ENTERGY NUCLEAR OPERATIONS, INC.

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

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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 1.0 gph 4- 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.0 gph

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

4- 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> NA

> 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 2 _7_

Control Room atmospheric dispersion (X/Q) factors Releases from containment surface('):

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

0- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/r 3 2- 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 4.92E-4 sec/r 3 8 - 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 2.06E4 sec/m3 24 - 96 hours0.00111 days <br />0.0267 hours <br />1.587302e-4 weeks <br />3.6528e-5 months <br /> 1.69E4 sec/n 3 96- 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> 1.26E-4 sec/rn3 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 XJQ values were corrected from the original determination. The revised values are sightly higher than those used in the dose analysis:

0- 2 hr 6.OOE-4 sec/m3 2- 8 hr 5.20E-4 sec/n3 8 - 24 hr 2.12E-4 sec/n3 24 - 96 hr 1.76E-4 sec/n?

96 - 720 hr 1.30E-4 sec/n?

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

Page 50 of 69 Updated Errata I

Table 21: Assumptions Used for Gas Decay Tank Rupture Dose Analysis Gas decay tank inventory 50,000 Ci of dose equivalent Xe- 133 Duration of release 5 minutes Control Room atmospheric dispersion (X/Q) factors Releases from containment ventl):

0- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/n 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.OOE-4 sec/m 3. I 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 Updated Errata I

Table 22: Assumptions Used for Volume Control Tank Rupture Dose Analysis Volume control tank inventory (Ci) 1-130 1.97E-2 1-131 6.29E-1 1-132 9.61E-1 I-133 1.14E0 1-134 2.33E-1 1-135 7.38E-I 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 pCi'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 ventd'":

0- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/n 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.OOE4 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 Updated Errata I

Table 23: Assumptions Used for Holdup Tank Failure Dose Analysis Holdup tank volume 8500 f 3 Holdup tank full level 80%/0 Reactor coolant iodine activity prior to accident 1.0 IiCi/grn 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 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('):

0- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 5.93E-4 sec/n 3 Note:

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 6.00 E-4 sec/rn?. I 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 Updated Errata I

Table 24: Assumptions Used for FHA 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%/o Other lodines and Noble Gases 100/%

Fuel Damaged One assembly Time after Shutdown 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br /> 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 <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> Time to Start Crediting Emergency Control Room HVAC 24 minutes Control Room Atmospheric Dispersion (X/Q) Factor Containment Ventdl):

0 - 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 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.OOE-4 sec/cn 3 . I 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 Updated Errata I

ATTACHMENT 7 TO NL-05-020 RESPONSE TO QUESTIONS REGARDING AST ENTERGY NUCLEAR OPERATIONS, INC.

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

NL-05-020 Attachment 7 Page 1 of 4 NRC QUESTION:

Please discuss the impact of postulated accidents occurring at IP3, on control room doses at the IP2 and vice versa.

ENTERGY RESPONSE:

A number of factors together demonstrate that for a postulated accident occurring at IP3 the doses in the IP2 control room would be lower than the doses calculated for the IP3 control room.

For releases from IP3, the XIQ values for IP3 to IP2 control room air intake are substantially lower than those for releases from IP3 to the IP3 control room air intake. XIQ values for IP3 releases to the IP2 control room range from 17 to 50 percent of the X/Q values for 1P3 releases to the IP3 control room.

Additionally, the IP2 control room air intake filter has an elemental iodine removal efficiency of 95% whereas the IP3 filter efficiency is 90%. The removal efficiencies for organic iodine and for particulates are the same for the two units.

During emergency mode operation, the IP2 control room air intake flow is Ž1800 cfm which is higher than the 21500 cfm associated with the IP3 control room. It has been determined as part of the IP3 radiological consequences analysis effort that a higher inflow has the effect of reducing the calculated doses.

Both the IP2 and the 1P3 control rooms have an assumed inleakage rate of 700 cfm so this is not a factor. While the IP2 control room volume of 102,400 cubic feet is substantially larger than the IP3 control room volume of 47,200 cubic feet, this does not significantly impact the doses. There is not expected to be a significant difference in the X/Q for the IP2 control room intake and potential inleakage locations as the ductwork for the IP2 HVAC is located above the control room not far from the intake location.

For accidents at IP2 and their effect on the IP3 Control Room, there is an additional approximate 695 feet between the release points at IP2 and the IP3 Control Room intake. Since the X/Q decreases with distance, the resultant doses would be much less than those projected for an accident at IP3.

The HVAC for each unit is activated by radiation monitors as well as safety injection signals on the respective units. In addition, the emergency plan requires notification of the other unit's control room in the event of an emergency.

There currently is no requirement to have the Control Room HVAC operable for IP2 during fuel handling (except for recently irradiated fuel) as the analysis for the Fuel Handling Accident takes no credit for its operation. Although the analysis submitted for the IP3 Fuel Handling Accident credited the HVAC, an evaluation shows that the 5 rem limit is still satisfied without crediting the operable HVAC.

A comparison of the XJQs for Unit 3 Releases to Unit 2 Control Room to X/Qs for Unit 2 Releases to Unit 2 Control Room shows that in all cases the XJQs for the Unit 2 releases are much greater than the XJQs for the Unit 3 releases. Since the source terms for both

NL-05-020 Attachment 7 Page 2 of 4 units are similar (see the attached table for calculated LBLOCA releases of nuclides that are significant for control room doses, i.e. 95% of the dose), the accident doses from Unit 3 at the Unit 2 Control Room would be expected to be less than those previously approved for the IP2 SPU.

Unit 3 Releases to Unit 3 Control Room 95% XIQ from ARCON96 Oto2 2to8 8to24 1 to4 4to30 Release Location hours hours hours days days Containment Surface 3.57E-04 3.12E-04 1.24E-04 1.06E-04 7.99E-05 Containment Vent 6.OOE-04 5.20E-04 2.12E-04 1.76E-04 1.30E-04 ABFB South Side 9.86E-04 8.74E-04 4.50E-04 3.50E-04 2.80E-04 ABFB SE Organ Pipe 1.14E-03 1.04E-03 5.05E-04 4.01E-04 3.21E-04 ABFB S Silencer 1.OOE-03 8.79E-04 4.41E-04 3.47E-04 2.78E-04 Unit 3 Releases to Unit 2 Control Room 95% XJQ from ARCON96 Release Location l Oto 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 22to8 hours T 8to24 hours l

l 1 to 4 days 44to30 1days Containment Surface 1.78E-04 1.38E-04 5.86E-05 3.79E-05 3.14E-05 Containment Vent 2.95E-04 2.25E-04 9.21 E-05 6.06E-05 4.87E-05 ABFB North Side 3.51E-04 2.15E-04 9.14E-05 6.33E-05 5.14E-05 ABFB NE Organ Pipe 3.49E-04 2.25E-04 9.75E-05 6.73E-05 5.43E-05 ABFB N Silencer l 3.32E-04 2.12E-04 9.26E-05 6.33E-05 5.14E-05 Unit 2 Releases to Unit 2 Control Room 95% XIQ from ARCON96 Oto2 l 2to8 8to24 1 to4 4to30 Release Location hours I hours I hours I days I days Containment Surface 3.82E-04 2.81 E-04 1.05E-04 8.31 E-051 7.04E-05 Auxiliary Boiler Feed South Side 1.09E-031 1.02E-03 4.99E-04 3.86E-04J 2.99E-04 Auxiliary Boiler Feed Stack 9.49E-041 8.65E-04 4.17E-04 3.30E-04 2.54E-04 Containment Vent 6.44E-04 4.69E-04 1.72E-04 1.37E-04l 1.17E-04

NL-05-020 Attachment 7 Page 3 of 4 SOURCE TERM COMPARISON FOR LBLOCA RELEASE IP3 LBLOCA Releases (Ci) 0-8 hr 8-24 hr 24-720 hr 1-131 8.883E+02 1.740E+02 4.856E+02 1-133 1.726E+03 2.367E+02 6.120E+01 1-135 1.404E+03 8.620E+01 3.800E+00 Cs-134 1.501E+02 2.402E+01 8.623E+01 Cs-137 8.718E+01 1.391E+01 5.075E+01 Te-132 1.677E+02 2.647E+01 1.486E+01 Sr-89 4.645E+01 8.060E+00 2.418E+01 Sr-90 4.625E+00 8.070E-01 2.946E+00 Ru-106 3.186E+00 5.555E-01 1.973E+00 Pu-238 5.412E-03 9.450E-04 3.449E-03 Pu-241 1.540E-01 2.688E-02 9.803E-02 1-131 4.453E+01 1.646E+02 2.549E+03 1-133 8.143E+01 2.140E+02 3.039E+02 IP2 LBLOCA Releases (Ci) 0-8 hr 8-24 hr 24-720 hr 1-131 9.448E+02 1.842E+02 4.880E+02 1-133 1.825E+03 2.500E+02 6.100E+01 1-135 1.478E+03 9.100E+01 4.OOOE+00 Cs-1 34 1.597E+02 2.580E+01 8.580E+01 Cs-1 37 9.229E+01 1.491E+01 5.020E+01 Te-1 32 1.768E+02 2.840E+01 1.490E+01 Sr-89 4.852E+01 8.600E+00 2.386E+01 Sr-90 4.814E+00 8.590E-01 2.895E+00 Ru-106 3.366E+00 5.990E-01 1.970E+00 Pu-238 5.686E-03 1.014E-03 3.420E-03 Pu-241 1.625E-01 2.890E-02 9.770E-02 1-131 6.907E+01 5.087E+02 3.282E+03 1-133 1.140E+02 6.551 E+02 5.469E+02 Ratio of IP3 to IP2 Releases 0-8 hr 8-24 hr 24-720 hr 1-131 94.0% 94.5% 99.5%

1-133 94.6% 94.7% 100.3%

1-135 95.0% 94.7% 95.0%

Cs-1 34 94.0% 93.1% 100.5%

Cs-1 37 94.5% 93.3% 101.1%

Te-132 94.9% 93.2% 99.7%

Sr-89 95.7% 93.7% 101.3%

Sr-90 96.1% 93.9% 101.8%

Ru-1 06 94.7% 92.7% 100.2%

Pu-238 95.2% 93.2% 100.8%

Pu-241 94.8% 93.0% 100.3%

1-131 64.5% 32.3% 77.7%

1-133 71.4% 32.7% 55.6%

Note: The iodines in the last two rows are for ECCS recirculation leakage, all other lines are for containment leakage.

NL-05-020 Attachment 7 Page 4 of 4 NRC QUESTION:

Please verify the content of meteorology files used for the AST analyses.

ENTERGY RESPONSE:

Data files for three years of meteorology data were transmitted electronically to NRC on 2/1/2005. These are the same files that had been previously transmitted for use in the Indian Point Unit 2 AST submittal. These files have been converted to ARCON96 format to degrees C1100 meters. The atmospheric stability categories were determined using the delta-T method. The measurement heights used were the 10 meter and 60 meter heights from the on-site tower.

NRC QUESTION:

Please verify that control room tracer gas testing supports the inleakage analysis assumptions used for AST.

ENTERGY RESPONSE:

The Vendor conducting the control room tracer gas test has reported the results. For the four tests performed in the incident (pressurization) mode, the results were 42 SCFM, 62 SCFM, 81 SCFM, and 88 SCFM with an analysis assumption of 700 CFM. For the Toxic Gas (Hazardous Chemical) mode, the result was 301 ACFM with an analysis assumption of 1300 CFM. For the Normal mode, the result was 1393 ACFM with an analysis assumption of a total 2200 CFM.

NRC QUESTION, '. '2r.'

Please provide the ARCON96 input/output log sheets for the IP3 release point to the IP2 control room calculation.  :

ENTERGY RESPONSE:

The requested information is provided in the attached pages excerpted from Calculation C-1 109298-03, Revision 0. The key to the five ARCON96 runs is as follows:

RUN ID IP3 SOURCE INTAKE.

IP3S06R2 Containment Surface Unit 2 Control Room IP3S02R2 Containment Vent Unit 2 Control Room IP3S07R2 Auxiliary Boiler Feed Building, North Side Unit 2 Control Room IP3S08R2 Auxiliary Boiler Feed Building, NE Organ Pipe Unit 2 Control Room IP3S09R2 Auxiliary Boiler Feed Building, North Silencer Unit 2 Control Room

I Calculation C-1109298-03 I Rev. 0l lFebruar 7, 2005 Page 10 of 29 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: jyll6nrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjhgnrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab29nrc.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 2/ 5/2005 at 10:54:01

..- .- INPUT ..........

ARCON Number of Meteorological Data Files . 3 Meteorological Data File Names C:\lP3Prime\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 (mW

  • 40.3 Building Area (m^2) 3059.3 Effluent vertical velocity (mis) * .00 Vent or stack flow (m'3/s) - .00 Vent or stack radius (m) * .00 Direction .. intake to source (deg) . 206 Wind direction sector width (deg) . 90 Wind direction window (deg)
  • 161 - 251 Distance to intake (m) - 134.3 Intake height (mW - 20.6 Terrain elevation difference (m} = .0 Output file names ip3sO6r2.log ip3sO6r2.cfd Minimum Wind Speed (m/s) * .5 Surface roughness length (m] . .10 Sector averaging constant - 4.0 Initial value of sigma y 17.32 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 - 6929 Hours elevated plume w/ dir. in window - 0 Hours of calm winds 361 Hours direction not in window or calm
  • 18844 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 1.00E-03 1.OOE-03 1.OOE-03 1.00E-03 1.00E-03 1.OOE-03 1.00E-03 1.OOE-03 LOW LIM. 1.00E-07 1.00E-07 1.00E-07 1.OOE-07 1.00E-07 1.OOE-07 1.OOE-07 1.OOE-07 1.00E-07 1.OOE-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 7290. 8839. 10801. 13298. 15149. 19089. 25091. 25424. 25378. 25002.

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

ZERO 18844. 17279. 15287. 12730. 10899. 6922. 750. 171. 0. 0.

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

% NON ZERO 27.89 33.84 41.40 51.09 58.16 73.39 97.10 99.33 100.00 100.00 95th PERCENTILE X/Q VALUES 1.78E-04 1.72E-04 1.63E-04 1.48E-04 1.22E-04 8.84E-05 5.06E-05 4.36E-05 3.77E-05 3.40E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 1.78E-04 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 1.38E-04 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 5.86E-05 1 to 4 days 3.79E-05 4 to 30 days 3.14E-05

ICalculation C-1109298-03 I Rev. 0 February 7, 2005 Page 11 of 29 HOURLY VALUE RANGE MAX X/Q MIN X/Q CENTERLINE 2.07E-04 1.67E-05 SECTOR-AVERAGE 1.29E-04 1.O5E-05 NORMAL PROGRAM COMPLETION

Calculation C-1109298-03 l Rev. 0 February 7 2005 Page 12 of 29 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: jyllgnrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjh9nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab2gnrc.gov Code Developer: J. V. Ra&msdell 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 2/ 4/2005 at 15:28:39

....... INPUT ..........

ARCON 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) = 76.2 Building Area (m^2) = 3059.3 Effluent vertical velocity (mWs) .00 Vent or stack flow Wm^3/s) = .00 Vent or stack radius (m) X .00 Direction .. intake to source (deg) = 206

,Wind direction sector width (deg) . 90 Wind direction window (deg) . 161 - 251 Distance to intake (m)

  • 141.5 Intake height (m) - 20.6 Terrain elevation difference (m) * .0 Output file names ip3sO2r2.log ip3sO2r2.cfd Minimum Wind Speed (m/s) . .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 = 6939 Hours elevated plume w/ dir. in window
  • 0 Hours of calm winds
  • 293 Hours direction not in window or calm - 18902 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 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 WI LIM. 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.00E-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 7232. 8761. 10714. 13230. 15105. 19053. 25091. 25424. 25378. 25002.

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

ZERO 18902. 17357. 15374. 12798. 10943. 6958. 750. 171. 0. 0.

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

3 NON ZERO 27.67 33.54 41.07 50.83 57.99 73.25 97.10 99.33 100.00 100.00 95th PERCENTILE X/Q VALUES 2.95E-04 2.84E-04 2.67E-04 2.42E-04 1.99E-04 1.42E-04 8.10E-05 6.97E-05 5.89E-05 5.30E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 2.95E-04 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.25E-04 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9.21E-05 1 to 4 days 6.06E-05 4 to 30 days 4.87E-05

ICalculationC-1109298-03 I Rev.O0 February 7, 2005 lPac13 of 29 HOURLY VALUE RANGE MAX X/Q IMNX/Q CENTERLINE 3.78E-04 1.81E-05 SECTOR-AVERAGE 2.37E-04 1.13E-05 NORMAL PROGRAM COMPLETION

l Calculation C-1109298-03 I Rev. 0° February 7, 2005 Page 14 of 291 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: jyllgnrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjhgnrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab28nrc.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 2/ 4(2005 at 15:28:39

....... INPUT ..........

ARCON Number of Meteorological Data Files

  • 3 Meteorological Data File Names C:\IP3Prime\IP-1995.MET C:\IP3Prime\IP_1996.MET C:\IP3Prime\IP_1997.M=^

Height of lower wind instrument (m)

  • 10.0 Height of upper wind instrument Im) = 60.0 Wind speeds entered as miles per hour Ground-level release Release height (m) = 10.3 Building Area (m2) = 3059.3 Effluent vertical velocity (m/s) = .00 Vent or stack flow Im'3/s) = .00 Vent or stack radius (m) * .00 Direction .. intake to source (deg) . 219 Wind direction sector width (deg) = 90 Wind direction window (deg) - 174 - 264 Distance to intake (m) . 118.9 Intake height (m) = 20.6 Terrain elevation difference (m) = .0 Output file names ip3sO7r2.log ip3sO7r2.cfd Minimum Wind Speed (m/s) . .5 Surface roughness length (m) . .10 Sector averaging constant - 4.0 Initial value of sigma y = 1.74 Initial value of sigma z . 1.21 Expanded output for code testing not selected Total number of hours of data processed
  • 26304 Hours of missing data 170 Hours direction in window = 4834 Hours elevated plume w/ dir. in window = 0 Hours of calm winds - 284 Hours direction not in window or calm - 21016 DISTRIBUTION

SUMMARY

DATA BY AVERAGING INTERVAL AVER. PER. 1 2 4 8 12 24 96 168 360 720 UPPER LIM. 1.00E-03 1.OOE-03 1.00E-03 1.OOE-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 1.00E-03 LOW LIM. 1.00E-07 1.00E-07 1.00E-07 1.00E-07 1.OGE-07 1.00E-07 1.0CE-07 1.00E-07 1.00E-07 1.OCE-07 ABOVE RANGE 0. 0. 0. 0. 0. 0. 0. 0. 0. 0.

IN RANGE 5118. 6788. 9081. 12154. 14471. 18749. 24942. 25364. 25378. 25002.

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

ZERO 21016. 19330. 17007. 13874. 11577. 7262. 899. 231. 0. 0.

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

% NON ZERO 19.58 25.99 34.81 46.70 55.56 72.08 96.52 99.10 100.00 100.00 95th PERCENTILE X/Q VALUES 3.51E-04 3.27E-04 2.84E-04 2.49E-04 2.03E-04 1.44E-04 8.35E-05 7.49E-05 6.33E-05 5.56E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3.51E-04 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.15E-04 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9.14E-05 1 to 4 days 6.33E-05 4 to 30 days 5.14E-05

Calculation C-1109298-03 I Rev. 0 IFebruary 7, 2005 1 Page 15 of 29d HOURLY VALUE RANGE MAX X/Q MIN XIQ CENTERLINE 5.58E-04 7.40E-OS SECTOR-AVERAGE 3.50E-04 4.63E-05 NORMAL PROGRAM COMPLETION

l Calculation C-1109298-03 l Rev. 0l February 7, 2005 Page 16 of 29 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: jyllgnrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjhgnrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab20nrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdell9pnl.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 2/ 4/2005 at 15:28:40 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) . .00 Vent or stack flow (m^3/s) = .00 Vent or stack radius (m) = .00 Direction .. intake to source (deg) = 216 1Wind direction sector width (deg) . 90 Wind direction window (deg) - 171 - 261 Distance to intake (m) . 129.7 Intake height (m) a 20.6 Terrain elevation difference (m) . .0 Output file names ip3sO8r2.log ip3sO8r2.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
  • 5203 Hours elevated plume w/ dir. in window . 0 Hours of calm winds . 284 Hours direction not in window or calm
  • 20647 DISTRIBUTION

SUMMARY

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

IN RANGE 5487. 7147. 9393. 12360. 14620. 18863. 24968. 25366. 25378. 25002.

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

ZERO 20647. 18971. 16695. 13668. 11428. 7148. 873. 229. 0. 0.

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

9 NON ZERO 21.00 27.36 36.01 47.49 56.13 72.52 96.62 99.11 100.00 100.00 95th PERCENTILE X/Q VALUES 3.49E-04 3.34E-04 2.92E-04 2.56E-04 2.08E-04 1.50E-04 8.8E-05 7.88E-05 6.58E-05 5.88E-05 95% XIQ for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3.49E-04 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.25E-04 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9.75E-05 1 to 4 days 6.73E-05 4 to 30 days 5.43E-05

ICalculation C-1109298-03 I Rev. 0 February 7, 2005 17 29 OrfPa HOURLY VALUE RANGE MAX X/O MIN X/0 CENTERLINE 5.08E-04 4.93E-05 SECTOR-AVERAGE 3.18E-04 3.09E-05 NORMAL PROGRAM COMPLETION

Calculation C-1109298-03 I Rev. 0 February 7, 2005 lPa c1 of 29 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: jyllenrc.gov J. J. Hayes Phone: (301) 415 3167 e-mail: jjh~nrc.gov L. A Brown Phone: (301) 415 1232 e-mail: lab2gnrc.gov Code Developer: J. V. Ramsdell Phone: (509) 372 6316 e-mail: jramsdellepnl.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 2/ 4/2005 at 15:28:40 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)
  • 29.0 Building Area (m2) . 3059.3 Effluent vertical velocity (mis) . .00 Vent or stack flow (m3/s) . .00 Vent or stack radius (m) .00 Direction .. intake to source (deg) = 216

'Wind direction sector width (deg) = 90 Wind direction window (deg) = 171 - 261 Distance to intake (m) . 134.3 Intake height (m)

  • 20.6 Terrain elevation difference (m) = .0 Output file names ip3sO9r2.log ip3sO9r2.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 = 5203 Hours elevated plume w/ dir. in window 0 Hours of calm winds = 284 Hours direction not in window or calm 20647 DISTRIBUTION

SUMMARY

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

IN RANGE 5487. 7147. 9393. 12360. 14620. 18863. 24968. 25366. 25378. 25002.

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

ZERO 20647. 18971. 16695. 13668. 11428. 7148. 873. 229. 0. 0.

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

E NON ZERO 21.00 27.36 36.01 47.49 56.13 72.52 96.62 99.11 100.00 100.00 95th PERCENTILE X/Q VALUES 3.32E-04 3.14E-04 2.76E-04 2.42E-04 1.97E-04 1.43E-04 8.31E-05 7.45E-05 6.21E-05 5.56E-05 95% X/Q for standard averaging intervals 0 to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 3.32E-04 2 to 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> 2.12E-04 8 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 9.26E-05 1 to 4 days 6.33E-05 4 to 30 days 5.14E-05

Calculation C-1109298-03 I Rev. 0l 1February 7, 2005 l Page 19 of 29 l HOURLY VALUE RANGE MAX X/Q miM X/Q CENTERLINE 4.76E-04 3.64E-05 SECTOR-AVERAGE 2.98E-04 2.28E-05 NORMAL PROGRAM COMPLETION

ATTACHMENT 8 TO NL-05-020 COMMITMENT LIST AND PROPOSED LICENSE CONDITION REGARDING INDIAN POINT 3 SPU ENTERGY NUCLEAR OPERATIONS, INC.

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

NL-05-020 Attachment 8 Page 1 of 2 ENTERGY COMMITMENTS AND PROPSED LICENSE CONDTION REGARDING INDIAN POINT 3 STRETCH POWER UPRATE LICENSE AMENDMENT COMMITMENT DESCRIPTION SCHEDULE ID NL-05-020-01 Entergy commits to revising Technical Specification Within 60 days of NRC Bases 3.4.3 to delete the reference to PTLR (which approval of IP3 SPU does not exist for IP3) and to clarify that the P/T license amendment curves are now based upon 34.0 EFPY instead of 34.7 EFPY. In addition, the basis for labeling the curves for 20 EFPY for applicability to the LTOPS arming temperature will be clarified.

NL-05-020-02 Entergy determined that the end-of-license projected fluence for the Indian Point 3 (IP3) RV internals will exceed the threshold of I X 102' n/cm2 (E> 0.1 MeV). Therefore, Entergy commits to the following:

Entergy is an active participant in the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP) research initiatives on aging-related degradation of reactor vessel internal components. For IP3, Entergy commits to:

A. Continue active participation in the EPRI MRP A. Ongoing research initiatives regarding aging-related degradation of reactor vessel internal components.

B. Evaluate the EPRI recommendations resulting B. Ongoing from this initiative and implement a reactor vessel internals degradation management program applicable to IP3.

C. Incorporate the results of reactor vessel C. Ongoing internals inspections into the IP3 augmented inspection plan, as appropriate.

D. Submit to NRC for review and approval, the D. March 2010 (Based augmented inspection plan that incorporates on five years from the inspection of the IP3 RV date of issuance of the IP3 SPU license amendment)

NL-05-020 Attachment 8 Page 2 of 2 PROPOSED LICENSE CONDITION:

With the reactor critical, Entergy shall maintain the reactor coolant system cold leg at a temperature (TcOld) greater than or equal to 525 OF. Entergy shall maintain a record of the cumulative time that the plant is operated with the reactor critical while TC',d is below 525 0F.

Upon determination by Entergy that the cumulative time of plant operation with the reactor critical while TcOId is below 525 OF has exceeded one (1) year, Entergy must:

(a) within one (1) month, inform the NRC, in writing, and (b) within six (6) months submit the results of an analysis of the impact of the operation with Tcold below 525 OF on the pressurized thermal shock reference temperature (RTPTS).

ENCLOSURE A TO NL-05-020 Westinghouse authorization letter dated February 9, 2005 (CAW-05-1951), with the accompanying affidavit, Proprietary Information Notice, and Copyright Notice ENTERGY NUCLEAR OPERATIONS, INC.

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

Westinn house Westinghouse Electric Company Nuclear Services P.O. Box 355 PittsburghPennsylvania 15230-0355 USA Direct tel: (412) 374-4643 U.S. Nuclear Regulatory Commission Direct fax: (412) 374-4011 Document Control Desk e-mail: greshaja~westinghouse.com Washington, DC 20555-0001 Our ref: CAW-05-1951 February 9, 2005 APPLICATION FOR WITHHOLDING PROPRIETARY INFORMATION FROM PUBLIC DISCLOSURE

Subject:

Responses to NRC Request forAdditional Information on WCAP-16212-P, Rev.

0, "Indian Point Nuclear Generating Unit No. 3 Stretch Power Uprate NSSS and BOP Licensing Report", dated February 2005 (Proprietary), TAC Number MC3552 The proprietary information for which withholding is being requested in the above-referenced report is further identified in Affidavit CAW-05-1951 signed by the owner of the proprietary information, Westinghouse Electric Company LLC. The affidavit, which accompanies this letter, sets forth the basis on which the information may be withheld from public disclosure by the Commission and addresses with specificity the considerations listed in paragraph (b)(4) of 10 CFR Section 2.390 of the Commission's regulations.

Accordingly, this letter authorizes the utilization of the accompanying affidavit by Entergy Nuclear Operations.

Correspondence with respect to the proprietary aspects of the application for withholding or the Westinghouse affidavit should reference this letter, CAW-05-1951, and should be addressed to J. A. Gresham, Manager, Regulatory Compliance and Plant Licensing, Westinghouse Electric Company LLC, P.O. Box 355, Pittsburgh, Pennsylvania 15230-0355.

Very truly yours,

. A. Gresham, Manager Regulatory Compliance and Plant Licensing Enclosures cc: B. Benney L. Feizollahi A BNFL Group company

CAW-05-1 951 AFFIDAVIT COMMONWEALTH OF PENNSYLVANIA:

Ss COUNTY OF ALLEGHENY:

Before me, the undersigned authority, personally appeared J. A. Gresham, who, being by me duly sworn according to law, deposes and says that he is authorized to execute this Affidavit on behalf of Westinghouse Electric Company LLC (Westinghouse), and that the averments of fact set forth in this Affidavit are true and correct to the best of his knowledge, information, and belief:

J. A. Gresham, Manager Regulatory Compliance and Plant Licensing Sworn to and subscrib d beforee this 9__ day of , 2005 Notary Public Notarial Sea)

Sharon L Fiod, Notary Pubic Monroeville Boro, AJIegheny County My Commission Expires January 29,2007 Member. Pennsylvaria Association Of Notaries

2 CAW-05-1 951 (1) I am Manager, Regulatory Compliance and Plant Licensing, in Nuclear Services, Westinghouse Electric Company LLC (Westinghouse), and as such, I have been specifically delegated the function of reviewing the proprietary information sought to be withheld from public disclosure in connection with nuclear power plant licensing and rule making proceedings, and am authorized to apply for its withholding on behalf of Westinghouse.

(2) I am making this Affidavit in conformance with the provisions of 10 CFR Section 2.390 of the Commission's regulations and in conjunction with the Westinghouse 'Application for Withholding" accompanying this Affidavit.

(3) I have personal knowledge of the criteria and procedures utilized by Westinghouse in designating information as a trade secret, privileged or as confidential commercial or financial information.

(4) Pursuant to the provisions of paragraph (b)(4) of Section 2.390 of the Commission's regulations, the following is furnished for consideration by the Commission in determining whether the information sought to be withheld from public disclosure should be withheld.

(i) The information sought to be withheld from public disclosure is owned and has been held in confidence by Westinghouse.

(ii) The information is of a type customarily held in confidence by Westinghouse and not customarily disclosed to the public. Westinghouse has a rational basis for determining the types of information customarily held in confidence by it and, in that connection, utilizes a system to determine when and whether to hold certain types of information in confidence. The application of that system and the substance of that system constitutes Westinghouse policy and provides the rational basis required.

Under that system, information is held in confidence if it falls in one or more of several types, the release of which might result in the loss of an existing or potential competitive advantage, as follows:

(a) The information reveals the distinguishing aspects of a process (or component, structure, tool, method, etc.) where prevention of its use by any

3 CAW-05-1 951 of Westinghouse's competitors without license from Westinghouse constitutes a competitive economic advantage over other companies.

(b) It consists of supporting data, including test data, relative to a process (or component, structure, tool, method, etc.), the application of which data secures a competitive economic advantage, e.g., by optimization or improved marketability.

(c) Its use by a competitor would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality, or licensing a similar product.

(d) It reveals cost or price information, production capacities, budget levels, or commercial strategies of Westinghouse, its customers or suppliers.

(e) It reveals aspects of past, present, or future Westinghouse or customer funded development plans and programs of potential commercial value to Westinghouse.

(f) It contains patentable ideas, for which patent protection may be desirable.

There are sound policy reasons behind the Westinghouse system which include the following:

(a) The use of such information by Westinghouse gives Westinghouse a competitive advantage over its competitors. It is, therefore, withheld from disclosure to protect the Westinghouse competitive position.

(b) It is information that is marketable in many ways. The extent to which such information is available to competitors diminishes the Westinghouse ability to sell products and services involving the use of the information.

(c) Use by our competitor would put Westinghouse at a competitive disadvantage by reducing his expenditure of resources at our expense.

4 CAW-05-1 951 (d) Each component of proprietary information pertinent to a particular competitive advantage is potentially as valuable as the total competitive advantage. If competitors acquire components of proprietary information, any one component may be the key to the entire puzzle, thereby depriving Westinghouse of a competitive advantage.

(e) Unrestricted disclosure would jeopardize the position of prominence of Westinghouse in the world market, and thereby give a market advantage to the competition of those countries.

(f) The Westinghouse capacity to invest corporate assets in research and development depends upon the success in obtaining and maintaining a competitive advantage.

(iii) The information is being transmitted to the Commission in confidence and, under the provisions of 10 CFR Section 2.390, it is to be received in confidence by the Commission.

(iv) The information sought to be protected is not available in public sources or available information has not been previously employed in the same original manner or method to the best of our knowledge and belief.

(v) The proprietary information sought to be withheld in this submittal is that which is appropriately marked in uResponses to NRC Request for Additional Information on WCAP-16212-P, Rev. 0, ulndian Point Nuclear Generating Unit No. 3 Stretch Power Uprate NSSS and BOP Licensing Report", dated February, 2005 (Proprietary)",

being transmitted by the Entergy Nuclear Northeast letter and Application for Withholding Proprietary Information from Public Disclosure, to the Document Control Desk. The proprietary information as submitted for use by Westinghouse for the Indian Point Nuclear Generating Unit No. 3 is specific to Indian Point Nuclear Generating Unit No. 3 in response to certain NRC requirements for justification of Stretch Power Uprate License Amendment Request.

This information is part of that which will enable Westinghouse to:

(a) Provide information in support of plant power uprate licensing submittals.

5 CAW-05-1 951 (b) Provide plant specific calculations.

(c) Provide licensing documentation support for customer submittals.

Further this information has substantial commercial value as follows:

(a) Westinghouse plans to sell the use of similar information to its customers for purposes of meeting NRC requirements for licensing documentation associated with power uprate licensing submittals.

(b) Westinghouse can sell support and defense of the technology to its customers in the licensing process.

(c) The information requested to be withheld reveals the distinguishing aspects of a methodology which was developed by Westinghouse.

Public disclosure of this proprietary information is likely to cause substantial harm to the competitive position of Westinghouse because it would enhance the ability of competitors to provide similar calculations, evaluations, analyses and licensing defense services for commercial power reactors without commensurate expenses.

Also, public disclosure of the information would enable others to use the information to meet NRC requirements for licensing documentation without purchasing the right to use the information.

The development of the technology described in part by the information is the result of applying the results of many years of experience in an intensive Westinghouse effort and the expenditure of a considerable sum of money.

In order for competitors of Westinghouse to duplicate this information, similar technical programs would have to be performed and a significant manpower effort, having the requisite talent and experience, would have to be expended.

Further the deponent sayeth not.

PROPRIETARY INFORMATION NOTICE Transmitted herewith are proprietary and/or non-proprietary versions of documents furnished to the NRC in connection with requests for generic and/or plant-specific review and approval.

In order to conform to the requirements of 10 CFR 2.390 of the Commission's regulations concerning the protection of proprietary information so submitted to the NRC, the information which is proprietary in the proprietary versions is contained within brackets, and where the proprietary information has been deleted in the non-proprietary versions, only the brackets remain (the information that was contained within the brackets in the proprietary versions having been deleted). The justification for claiming the information so designated as proprietary is indicated in both versions by means of lower case letters (a) through (f) located as a superscript immediately following the brackets enclosing each item of information being identified as proprietary or in the margin opposite such information. These lower case letters refer to the types of information Westinghouse customarily holds in confidence identified in Sections (4)(ii)(a) through (4)(ii)(f) of the affidavit accompanying this transmittal pursuant to 10 CFR 2.390(b)(1).

COPYRIGHT NOTICE The reports transmitted herewith each bear a Westinghouse copyright notice. The NRC is permitted to make the number of copies of the information contained in these reports which are necessary for its internal use in connection with generic and plant-specific reviews and approvals as well as the issuance, denial, amendment, transfer, renewal, modification, suspension, revocation, or violation of a license, permit, order, or regulation subject to the requirements of 10 CFR 2.390 regarding restrictions on public disclosure to the extent such information has been identified as proprietary by Westinghouse, copyright protection notwithstanding. With respect to the non-proprietary versions of these reports, the NRC is permitted to make the number of copies beyond those necessary for its internal use which are necessary in order to have one copy available for public viewing in the appropriate docket files in the public document room in Washington, DC and in local public document rooms as may be required by NRC regulations if the number of copies submitted is insufficient for this purpose.

Copies made by the NRC must include the copyright notice in all instances and the proprietary notice if the original was identified as proprietary.

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