ML101810435

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Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML101810435
Person / Time
Site: Millstone, Kewaunee, Surry, North Anna  Dominion icon.png
Issue date: 06/29/2010
From: Price J
Dominion, Dominion Energy Kewaunee, Dominion Nuclear Connecticut, Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
10-384, FOIA/PA-2011-0115
Download: ML101810435 (27)
v • d • e


Text

Dominion Resources Services, Inc.

5000 D om inio n Boulevard, Glen Allen, VA 230 60

~~

Dominion Web Address: www.dom.com June 29, 2010 U.S. Nuclear Regulatory Commission Serial No.10-384 Attention: Document Control Desk NL&OS/ETS R1 Washington , DC 20555 Docket Nos. 50-305 50-336/423 50-338/339 50-280/281 License Nos. DPR-43 DPR-65/NPF-49 NPF-4/7 DPR-32/37 DOMINION ENERGY KEWAUNEE, INC.

DOMINION NUCLEAR CONNECTICUT, INC.

VIRGINIA ELECTRIC AND POWER COMPANY KEWAUNEE POWER STATION MILLSTONE POWER STATION UNITS 2 AND 3 NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 2009 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 In accordance with 10 CFR 50.46(a)(3)(ii), Dominion Energy Kewaunee , Inc. (DEK),

Dominion Nuclear Connecticut, Inc. (DNC) and Virginia Electric and Power Company (Dominion) hereby submit the annual summary of permanent changes to the emergency core cooling system (ECCS) evaluation models for Kewaunee Power Station (KPS), Millstone Power Station (MPS) Units 2 and 3, North Anna Power Station (NAPS) Units 1 and 2, and Surry Power Station (SPS) Units 1 and 2, respectively. of this letter provides a report describing plant-specific evaluation model changes associated with the Westinghouse and AREVA Small Break Loss of Coolant Accident (SBLOCA) and Large Break Loss of Coolant Accident (LBLOCA) ECCS evaluation models for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2.

Information regarding the effect of the ECCS evaluation model changes upon the reported SBLOCA and LBLOCA analyses of record (AOR) results is provided for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2 in Attachments 2,3,4 and 5, respectively.

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 Page 2 of 4 The calculated peak cladding temperatures (PCT) for the SBLOCA and LBLOCA analyses for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2 are summarized below.

Kewaunee - Small break - Westinghouse Evaluation Model: 106S0F Kewaunee - Large break - Westinghouse Evaluation Model: 204S0F Millstone Unit 2 - Small break - AREVA Evaluation Model: 1718°F Millstone Unit 2 - Large break - AREVA Evaluation Model: 184soF Millstone Unit 3 - Small break - Westinghouse Evaluation Model: 1193°F Millstone Unit 3 - Large break - Westinghouse Evaluation Model: 1781°F North Anna Unit 1 - Small break - AREVA Evaluation Model: 139SOF North Anna Unit 1 - Large break - AREVA Evaluation Model: 1866°F North Anna Unit 2 - Small break - AREVA Evaluation Model: 1338°F North Anna Unit 2 - Large break - AREVA Evaluation Model: 1878°F Surry Units 1 and 2 - Small break - Westinghouse Evaluation Model: 2012°F Surry Units 1 and 2 - Large break - Westinghouse Evaluation Model: 18srF The LOCA results for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2 are confirmed to have sufficient margin to the 2200°F limit for PCT specified in 10 CFR S0.46. Based on the evaluation of this information and the resulting changes in the applicable licensing basis PCT results, no further action is required to demonstrate compliance with the 10 CFR S0.46 requirements.

This information satisfies the 2009 annual reporting requirements of 10 CFR S0.46(a)(3)(ii).

If you have any further questions regarding this submittal , please contact Mr. Thomas Shaub at (804) 273-2763.

Very truly yours, J. Ian rice Vi e Pr sident - Nuclear Engineering Do . ion Energy Kewaunee, Inc.

Dominion Nuclear Connecticut, Inc.

Virginia Electric and Power Company Commitments made in this letter:

1. None.

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 Page 3 of 4 Attachments: (5)

1) Report of Changes in Westinghouse and AREVA ECCS Evaluation Models.
2) 2009 Annual Report of 10 CFR 50.46 Margin Utilization - Kewaunee Power Station.
3) 2009 Annual Report of 10 CFR 50.46 Margin Utilization - Millstone Power Station Units 2 and 3.
4) 2009 Annual Report of 10 CFR 50.46 Margin Utilization - North Anna Power Station Units 1 and 2.
5) 2009 Annual Report of 10 CFR 50.46 Margin Utilization - Surry Power Station Units 1 and 2.

cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, Pennsylvania 19406-1415 U.S. Nuclear Regulatory Commission Region II Marquis One Tower 245 Peachtree Center Avenue, NE Suite 1200 Atlanta , Georgia 30303 -1257 U.S. Nuclear Regulatory Commission Region III 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 NRC Senior Resident Inspector Kewaunee Power Station NRC Senior Resident Inspector Millstone Power Station NRC Senior Resident Inspector North Anna Power Station NRC Senior Resident Inspector Surry Power Station

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 Page 4 of 4 cc: (continued)

Mr. K. D. Feintuch NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 H4A 11555 Rockville Pike Rockville , Maryland 20852-2738 Ms. C. J. Sanders NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 83 11555 Rockville Pike Rockville, MD 20852-2738 Dr. V. Sreenivas NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville , Maryland 20852-2738

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 ATTACHMENT 1 2009 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 REPORT OF CHANGES IN WESTINGHOUSE AND AREVA ECCS EVALUATION MODELS DOMINION ENERGY KEWAUNEE, INC.

DOMINION NUCLEAR CONNECTICUT, INC.

VIRGINIA ELECTRIC AND POWER COMPANY KEWAUNEE POWER STATION MILLSTONE POWER STATION UNITS 2 AND 3 NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 1 of 4 REPORT OF CHANGES IN WESTINGHOUSE AND AREVA ECCS EVALUATION MODELS Kewaunee Power Station (KPS)

1. Westinghouse identified no changes or errors affecting the 1985 Westinghouse Small Break Loss of Coolant Accident (SBLOCA) Evaluation Model (EM) with NOTRUMP for KPS.
2. Westinghouse identified the following changes and errors applicable to the KPS 1999 Westinghouse Best Estimate (BE) Large Break (LB) LOCA Evaluation Model (EM) with application to Pressurized Water Reactors (PWR) with upper plenum injection:
  • General Code Maintenance
  • Discrepancy in Metal Masses Used From Drawings (Lower Support Plate).

The updated lower support plate metal masses have been evaluated for impact on current licensing basis analysis results and will be incorporated on a forward fit basis.

  • HOTSPOT Gap Heat Transfer Logic The HOTSPOT code has been updated to incorporate the following changes to the gap heat transfer logic: (1) change the gap temperature from the pellet average temperature to the average of the pellet outer surface and the clad inner surface; (2) correct the calculation of pellet surface emissivity to use a temperature in 0 R instead of 0 F; and (3) revise the calculation of the gap radiation heat transfer coefficient.
  • HOTSPOT Statistical Output Logic Update to the HOTSPOT code to (1) revise one of the three methods for calculating the standard deviation of cladding temperature to correctly identify the bin containing the 97.5 th percentile value and (2) change the 50 th, 95 th and 97.5 th bin values from the lower end of the range to the upper end.

These items were evaluated to have a 0 0 F impact on peak centerline temperature (PCT) .

Millstone Power Station Unit 2 (MPS 2)

1. AREVA identified the following changes and errors applicable to the S-RELAP5 based SBLOCA evaluation model for MPS 2.
  • RELAP5 Kinetics and Heat Conduction Model.

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 2 of 4 This item is a correction to the RELAP based codes recommended by Idaho 0

National Laboratory (INL). This item was evaluated to have a +4 F impact on PCT.

  • RODEX2 Thermal Conductivity Degradation An error was corrected in the use of the incorrect heat capacity when evaluating a right boundary mesh point. Instead of using the last (adjacent) mesh heat capacity, the heat capacity of the next to last mesh heat capacity was used.

This item was evaluated to have a 0 0 F impact on PCT for SBLOCA.

2. AREVA identified the following changes and errors applicable to the SEM/PWR-98 evaluation model for LBLOCA for MPS 2.
  • Notification of Non-Conservative RODEX Fuel Pellet Temperature This condition report addresses an issue with the RODEX2 code wherein burnup dependent thermal conductivity is not accounted for. The code may have under-predicted the fuel pellet temperatures at burnup beyond 20 GWd/MTU. This item was evaluated to have a +20 0 F impact on the LBLOCA analysis.

Millstone Power Station Unit 3 (MPS 3)

1. Westinghouse identified no changes , error corrections, or enhancements to the 1985 Westinghouse SBLOCA EM with NOTRUMP.
2. Westinghouse identified the following changes and errors applicable to the 2004 Westinghouse BE-LBLOCA EM using the Automated Statistical Treatment of Uncertainty Method (ASTRUM) for MPS 3:
  • General Code Maintenance
  • Error in ASTRUM Processing of Average Rod Burnup and Rod Internal Pressure Correction of an error in the processing of the burnup and rod internal pressure for average core rods in ASTRUM analyses. The correction of the error has been evaluated for the impact on current licensing basis analyses and will be incorporated into the ASTRUM method at a future time.
  • Discrepancy in Metal Masses Used From Drawings The updated lower support plate metal masses have been evaluated for impact on current licensing basis analysis results and will be incorporated on a forward fit basis.

Serial Number 10*384 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 3 of 4

  • HOTSPOT Gap Heat Transfer Logic The HOTSPOT code has been updated to incorporate the following changes to the gap heat transfer logic: (1) change the gap temperature from the pellet average temperature to the average of the pellet outer surface and the clad inner surface ; (2) correct the calculation of pellet surface emissivity to use a temperature in 0 R instead of 0 F; and (3) revise the calculation of the gap radiation heat transfer coefficient.

These items were evaluated to have a 0 0 F impact on PCT.

North Anna Power Station (NAPS) Units 1 and 2

1. AREVA evaluated the following changes in the SBLOCA evaluation models for NAPS Units 1 and 2:
  • RELAP5 Code heat conduction solution and its impact on reactor kinetics This item is a correction to the RELAP based codes recommended by INL.

This item was evaluated to have a 0 °F impact on PCT for SBLOCA.

  • TAC03 - treatment of burnup dependence of thermal conductivity The evaluation determined that the SBLOCA analyses are unaffected as the fuel remains in single phase or nucleate boiling heat transfer regimes early in the event. This item was evaluated to have a 0 °F impact on PCT for SBLOCA.
2. AREVA identified the following changes and errors applicable to the Realistic LBLOCA EM, RELAP5 based evaluation model for NAPS Units 1 and 2.
  • RELAP5 Kinetics and Heat Conduction Model This item is a correction to the RELAP based codes recommended by INL. This item was evaluated to have a-29 °F impact on PCT on each of the NAPS units.
  • RODEX2 Thermal Conductivity Degradation This condition report addresses an issue with the RODEX2 code wherein burnup dependent thermal conductivity is not accounted for. The code may have under-predicted the fuel pellet temperatures at burnup beyond 20 GWdlMTU. This item was evaluated to have a 0 °F impact on PCT for RLBLOCA EM.

Implementation will result in a +2 °F PCT impact for NAPS Unit 1 and has resulted in a +20 °F PCT impact for NAPS Unit 2.

Serial Number 10-384 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 4 of 4 Surry Power Station (SPS) Units 1 and 2

1. Westinghouse identified no changes , error corrections, or enhancements to the 1985 Westinghouse SBLOCA EM with NOTRUMP .
2. Westinghouse identified the following changes and errors applicable to the 2004 Westinghouse BE-LBLOCA EM using the Automated Statistical Treatment of Uncertainty Method (ASTRUM) for SPS 1 and 2:
  • General Code Maintenance
  • Error in ASTRUM Processing of Average Rod Burnup and Rod Internal Pressure Correction of an error in the processing of the burnup and rod internal pressure for average core rods in ASTRUM analyses. The correction of the error has been evaluated for the impact on current licensing basis analyses and will be incorporated into the ASTRUM method at a future time.
  • Discrepancy in Metal Masses Used From Drawings The updated lower support plate metal masses have been evaluated for impact on current licensing basis analysis results and will be incorporated on a forward fit basis. .
  • HOTSPOT Gap Heat Transfer Logic The HOTSPOT code has been updated to incorporate the following changes to the gap heat transfer logic: (1) change the gap temperature from the pellet average temperature to the average of the pellet outer surface and the clad inner surface; (2) correct the calculation of pellet surface emissivity to use a temperature in 0 R instead of 0 F; and (3) revise the calculation of the gap radiation heat transfer coefficient.

These items were evaluated to have a 0 0 F impact on PCT.

Conclusion The LOCA results for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2 are confirmed to have sufficient margin to the 2200 °F limit for PCT specified in 10 CFR 50.46. Based on the evaluation of this information and the resulting changes in the applicable licensing basis PCT results, no further action is required to demonstrate compliance with the 10 CFR 50.46 requirements. Reporting of this information is required per 10 CFR 50.46(a)(3)(ii), which obligates each licensee to report the effect upon calculated temperature of any change or error in evaluation models or their application on an annual basis.

Serial Number 10-384 Docket No. 50-305 ATTACHMENT 2 2009 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2009 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION

Number 10-384 Docket No. 50-305 Attachment 2, Page 1 of 2 10 CFR 50.46 MARGIN UTILIZATION - SMALL BREAK LOCA Plant Name: Kewaunee Power Station Utility Name: Dominion Energy Kewaunee, Inc.

Analysis Information EM: NOTRUMP Limiting Break Size: 3 Inch Cl, High Tav Analysis Date: 05/14/02 Vendor: Westinghouse FQ: 2.5 FdH: 1.8 Fuel: 422 Vantage + SGTP(%): 10 Notes: Uprate to 1772 MWt. Effective beginning Cycle 26 LICENSING BASIS Analysis of Record PCT 1030 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Reactor Coolant Pump Reference Conditions 0
2. Pressurizer Fluid Volumes 0
3. lower Guide Tube Assembly Weight 0
4. Discrepancy in NOTRUMP REST Draindown Calculation 0
5. NOTRUMP Bubble Rise/Drift Flux Model 35 Inconsistency Corrections
6. NOTRUMP-EM Refined Break Spectrum 0
7. Errors in Reactor Vessel Nozzle Data Collections 0
8. Pump Weir Resistance Modeling 0
9. Errors in Reactor Vessel lower Plenum Surface 0 Area Calculations
10. Discrepancy in Metal Masses Used from Drawings 0 B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1065

Number 10-384 Docket No. 50-305 Attachment 2, Page 2 of 2 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name: Kewaunee Power Station Utility Name: Dominion Energy Kewaunee , Inc.

Analysis Information EM: UPI (1999) Limiting Break Size: Split Analysis Date: 03/25/02 Vendor: Westinghouse Fa: 2.5 FdH: 1.8 Fuel: 422 Vantage + SGTP(%): 10 Notes: Uprate to 1772 MWt. Effective beginning Cycle 26 Clad Temp COF)

LICENSING BASIS Analysis of Record PCT 2084 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

. 1. Pressurizer Fluid Volumes o

2. Vessel Unheated Conductor Noding o
3. Level Boundary Selection o
4. Containment Relative Humidity Assumption o
5. Diffuser Plate Modeling o
6. Downcomer Momentum Area o
7. Revised Blowdown Heatup Uncertainty Distribution 5
8. Spacer Grid Heat Transfer Model Inputs 5
09. Inconsistent Vessel Vertical Level Modeling o
10. Revised Downcomer Gap Inputs -59
11. Core Support Column Heat Slab Discrepancy o
12. HOTSPOT Fuel Relocation Error 10
13. Revised Upper Plenum Volume Inputs o
14. Steam Generator Nozzle Volume Accounting Error o
15. Errors in Reactor Vessel Nozzle Data Collections o
16. Lower Plenum Unheated Conductors o
17. HOTSPOT Burst Temperature Logic Errors o B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. Discrepancy in Metal Masses Used From Drawings o

. (Lower Support Plate)

2. HOTSPOT Gap Heat Transfer Logic o
3. HOTSPOT Statistical Output Logic o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 2045

Serial Number 10-384 Docket Nos. 50-336/423 ATTACHMENT 3 2009 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2009 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 2 AND 3

Serial Number 10-384 Docket Nos. 50-336/423 Attachment 3, Page 1 of 4 10 CFR 50.46 MARGIN UTILIZATION - SMALL BREAK LOCA Plant Name: Millstone Power Station , Unit 2 Utility Name: Dominion Nuclear Connecticut, Inc.

Analysis Information EM: PWR Small Break LOCA, Limiting Break Size: 0.08 ft2 S-RELAP5 Based Analysis Date: 01/02 Vendor: AREVA Peak Linear Power: 15.1 kW/ft Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1941 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Decay Heat Model Error -133
2. Revised SBLOCA Guideline o
3. Core Exit Modeling-Upper Tie Plate Flow Area -22
4. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -8
5. S-RELAP5 Choked Flow Error with Non-Condensibles Present o
6. Radiation to Fluid Heat Transfer Model Change -64 B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. RELAP5 Kinetics and Heat Conduction Model 4
2. RODEX2 Thermal Conductivity Degradation o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1718

Serial Number 10-384 Docket Nos. 50-336/423 Attachment 3, Page 2 of 4 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name: Millstone Power Station, Unit 2 Utility Name: Dominion Nuclear Connecticut, Inc.

Analysis Information EM: SEM/PWR-98 Limiting Break Size: 1.0 DECLG Analysis Date: 11/98 Vendor: AREVA Peak Linear Power: 15.1 kW/ft Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1814 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Corrected Corrosion Enhancement Factor -1
2. ICECON Coding Errors 0
3. Setting RFPAC Fuel Temperatures at Start of Reflood -2
4. SISPNCH/ujun98 Code Error 0
5. Error in Flow Blockage Model in TOODEE2 0
6. Change in TOODEE2-Calculation of QMAX 0
7. Change in Gadolinia Modeling 0
8. PWR LBLOCA Split Break Modeling 0
9. TEOBY Calculation Error 0
10. Inappropriate Heat Transfer in TOODEE2 0
11. End-of-Bypass Prediction by TEOBY 0
12. R4SS Overwrite of Junction Inertia 0
13. Incorrect Junction Inertia Multipliers 1
14. Errors Discovered During RODEX2 V&V 0
15. Error in Broken Loop SG Tube Exit Junction Inertia 0
16. RFPAC Refill and Reflood Calculation Code Errors 16 .
17. Incorrect Pump Junction Area Used in RELAP4 0
18. Error in TOODEE2 Clad Thermal Expansion -1
19. Accumulator Line Loss Error -1
20. Inconsistent Loss Coefficients Used for Robinson LBLOCA 0
21. Pump Head Adjustment for Pressure Balance Initialization -3
22. ICECON Code Errors 0
23. Containment Sump Modification and Replacement PZR 2 B. Planned Plant Modification Evaluations
1. None 0 C. 2009 ECCS Model Assessments
1. Non-Conservative RODEX Fuel Pellet Temperature 20 D. Other
1. None 0 LICENSING BASIS peT + PCT ASSESSMENTS PCT = 1845

Serial Number 10-384 Docket Nos. 50-336/423 Attachment 3, Page 3 of 4 10 CFR 50.46 MARGIN UTILIZATION - SMALL BREAK LOCA Plant Name: Millstone Power Station, Unit 3 Utility Name: Dominion Nuclear Connecticut, Inc.

Analysis Information EM: NOTRUMP Limiting Break Size: 4 Inches Analysis Date: 02/07/07 Vendor: Westinghouse FQ: 2.6 Fi1H: 1.65 Fuel: RFA-2 SGTP (%): 10 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1193 PCT ASSESSM ENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Errors in Reactor Vessel Lower Plenum Surface Area Calculations 0
2. Discrepancy in Metal Masses Used From Drawings 0 B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1193

SerialNumber1~384 Docket Nos. 50-336/423 Attachment 3, Page 4 of 4 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name: Millstone Power Station, Unit 3 Utility Name: Dominion Nuclear Connecticut, Inc.

Analysis Information EM: ASTRUM (2004) Limiting Break Size: Guillotine Analysis Date: 04/17/07 Vendor: Westinghouse FQ: 2.6 F~H: 1.65 Fuel: RFA-2 SGTP (%): 10 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1781 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. HOTSPOT Burst Temperature Logic Errors o
2. CCFL Global Volume Error o B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. HOTSPOT Gap Heat Transfer Logic o
2. Discrepancy in Metal Masses Used From Drawings o
3. Error in ASTRUM Processing of Average Rod Burnup o and Rod Internal Pressure D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1781

Serial Number 10-384 Docket Nos. 50-338/339 ATTACHMENT 4 2009 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2009 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2

Serial Number 10-384 Docket Nos. 50-338/339 Attachment 4, Page 1 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA SMALL BREAK LOCA Plant Name: North Anna Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: AREVA SB EM Limiting Break Size: 5.2 Inches (SI Line)

Analysis Date: 2004 Vendor: . AREVA FQ: 2.32 F.1H: 1.65 Fuel: Advanced Mark-BW SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1404 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments 1.. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -8

2. RCCA Reactivity Input -3
3. Critical Flow Transition 26 B. Planned Plant Modification Evaluations
1. Revised Test Flow Curve for HHSI -24
2. Advanced Mark BW Top Nozzle Modification o C. 2009 ECCS Model Assessments
1. RELAP5 Kinetics and Heat Conduction Model o
2. TAC03 - Thermal Conductivity Degradation o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1395

Serial Number 10-384 Docket Nos. 50-338/339 Attachment 4, Page 2 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA LARGE BREAK LOCA Plant Name: North Anna Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: AREVA RLBLOCA EM Limiting Break Size: DEGB Analysis Date: 2004 Vendor: AREVA Fa: 2.32 F,1H: 1.65 Fuel: MixedNAIF/Advanced Mark-BW SGTP (%): 12 NAIF/Advanced Mark-BW Notes: Only AREVA fuel in core analysis bounds both Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1853 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Forslund-Rohsenow Correlation Modeling 64
2. RWST Temperature Assumption 8
3. LBLOCA/Seismic SG Tube Collapse o
4. ICECON Code Errors o
5. RLBLOCA Choked Flow Disposition -26
6. RLBLOCA Changes in Uncertainty Parameters 10
7. Blowdown Quench o
8. Mixture Level Model Limitation in the S-RELAP5 Code -29
9. Point Kinetics Programming Issue -20 with RELAP5-Based Computer Codes
10. Cold Leg Condensation Under Predicted by o S-RELAP5
11. Cross-Flow Junction Area in S-RELAP o Model
12. Radiation to Fluid Heat Transfer Model Change -32 B. Planned Plant Modification Evaluations
1. Advanced Mark-BW Top Nozzle Modification 65
2. GSI-191 Sump Strainer o
3. MUR Implementation 2 C. 2009 ECCS Model Assessments
1. S-RELAP5 Kinetics and Heat Conduction Model -29
2. RODEX3A - Thermal Conductivity Degradation o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1866

Serial Number 10-384 Docket Nos. 50-338/339 Attachment 4, Page 3 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA SMALL BREAK LOCA Plant Name: North Anna Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analysis Information EM: AREVA SB EM Limiting Break Size: 3 Inches Analysis Date: 2004 Vendor: AREVA FQ: 2.32 Fi\H: 1.65 Fuel: Advanced Mark-BW SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1370 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -8
2. RCCA Reactivity Input -29
3. Critical Flow Transition 5 B. Planned Plant Modification Evaluations
1. Advanced Mark BW Top Nozzle Modification o C. 2009 ECCS Model Assessments
1. RELAP5 Kinetics and Heat Conduction Model o
2. TAC03 - Thermal Conductivity Degradation o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1338

Serial Number 10-384 Docket Nos. 50-338/339 Attachment 4, Page 4 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA LARGE BREAK LOCA Plant Name: North Anna Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analysis Information EM: AREVA RLBLOCA EM Limiting Break Size: DEGB Analysis Date: 2004 Vendor: AREVA FQ: 2.32 FilH: 1.65 Fuel: Mixed - NAIF/Advanced Mark-BW SGTP (%): 12 NAIF/Advanced Mark-BW Notes: Only AREVA fuel in core analysis bounds both Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1789 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. Forslund-Rohsenow Correlation Modeling 64
2. RWST Temperature-Assumption 8
3. LBLOCA/Seismic SG Tube Collapse 0
4. ICECON Code Errors 0
5. RLBLOCA Choked Flow Disposition 22
6. RLBLOCA Changes in Uncertainty Parameters 10
7. Mixture Level Model Limitation in the S-RELAP5 Code -19
8. Point Kinetics Programming Issue -20 with RELAP5-Based Computer Codes
9. Cold Leg Condensation Under Predicted by S-RELAP5 0
10. Cross-Flow Junction Area in S-RELAP Model 0
11. Radiation to Fluid Heat Transfer Model Change -32 B. Planned Plant Modification Evaluations
1. Advanced Mark-BW Top Nozzle Modification 65
2. GSI-191 Sump Strainer o
3. MUR Implementation 20 C. 2009 ECCS Model Assessments
1. S-RELAP5 Kinetics and Heat Conduction Model -29
2. RODEX3A - Thermal Conductivity Degradation o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1878

Serial Number 10-384 Docket Nos. 50-280/281 ATTACHMENT 5 2009 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2009 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2

Serial Number 10-384 Docket Nos. 50-280/281 Attachment 5, Page 1 of 4 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name: Surry Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: NOTRUMP Limiting Break Size: 2.75 Inches Analysis Date: 5/7/2009 Vendor: Westinghouse FQ: 2.5 F~H: 1.7 Fuel: SIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 2012 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. None o B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2012

Serial Number 10-384 Docket Nos. 50-280/281 Attachment 5, Page 2 of 4 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA WITH ASTRUM Plant Name: Surry Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: ASTRUM (2004) Limiting Break Size: DEG Analysis Date: 11/3/08 Vendor: Westinghouse FQ: 2.5 FAH: 1.7 Fuel: OFA SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1857 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. HOTSPOT Burst Temperature Logic Errors o B. Planned Plant Modification Evaluations
1. Evaluation of Additional Containment Metal o C. 2009 ECCS Model Assessments
1. Error in ASTRUM Processing of Average Rod Burnup o and Rod Internal Pressure
2. Discrepancy in Metal Masses Used From Drawings o
3. HOTSPOT Gap Heat Transfer Logic o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1857

Serial Number 10-384 Docket Nos. 50-280/281 Attachment 5, Page 3 of 4 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name: Surry Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analysis Information EM: NOTRUMP Limiting Break Size: 2.75 Inches Analysis Date: 5/7/2009 Vendor: Westinghouse FQ: 2.5 F~H: 1.7 Fuel: SIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 2012 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. None o B. Planned Plant Modification Evaluations
1. None o C. 2009 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2012

Serial Number 10-384 Docket Nos. 50-280/281 Attachment 5, Page 4 of 4 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA WITH ASTRUM Plant Name: Surry Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analysis Information EM: ASTRUM (2004) Limiting Break Size: DEG Analysis Date: 11/3/08 Vendor: Westinghouse FQ: 2.5 FilH: 1.7 Fuel: OFA SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1857 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. HOTSPOT Burst Temperature Logic Errors o B. Planned Plant Modification Evaluations
1. Evaluation of Additional Containment Metal o C. 2009 ECCS Model Assessments
1. Error in ASTRUM Processing of Average Rod Burnup o and Rod Internal Pressure
2. Discrepancy in Metal Masses Used From Drawings o
3. HOTSPOT Gap Heat Transfer Logic o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1857
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