ML081790437

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Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML081790437
Person / Time
Site: Millstone, Kewaunee, Surry, North Anna  Dominion icon.png
Issue date: 06/26/2008
From: Gerald Bichof
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
08-0348
Download: ML081790437 (32)
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Text

Dominion Resources Services, Inc.

'iOOO Dominion Boulevard, Glen Allen, VA 2:'i(l('I!

\V"h Address: www.dom.com June 26, 2008 U.S. Nuclear Regulatory Commission Serial No. 08-0348 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. (DEK)

DOMINION NUCLEAR CONNECTICUT, INC. (DNC)

VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION)

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 2007 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 In accordance with 10 CFR 50.46(a)(3)(ii), DEK, DNC, and 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.

Attachment 1 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. The cores at NAPS 1 and 2 were comprised of both Westinghouse fuel and AREVA fuel in 2007. Therefore, there are two sets of margin utilization data for NAPS 1 and 2. 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

Serial No. 08-0348 Annual 50.46 ECCS Model Changes Docket Nos.: 50-305, 336/423, 338/339, 280/281 Page 2 of 4 summarized below:

Kewaunee - Small break - Westinghouse Evaluation Model: 1065°F Kewaunee - Large break - Westinghouse Evaluation Model: 2045°F Millstone Unit 2 - Small break - AREVA Evaluation Model: 1778°F Millstone Unit 2 - Large break - AREVA Evaluation Model: 1825°F Millstone Unit 3 - Small break - Westinghouse Evaluation Model: 1009°F Millstone Unit 3 - Large break - Westinghouse Evaluation Model: 208rF North Anna Unit 1 - Small break - Westinghouse Evaluation Model: 1809°F North Anna Unit 1 - Large break - Westinghouse Evaluation Model: 2131°F North Anna Unit 1 - Small break - AREVA Evaluation Model: 1372°F North Anna Unit 1 - Large break - AREVA Evaluation Model: 1925°F North Anna Unit 2 - Small break - Westinghouse Evaluation Model: 1809°F North Anna Unit 2 - Large break - Westinghouse Evaluation Model: 2131°F North Anna Unit 2 - Small break - AREVA Evaluation Model: 1362°F North Anna Unit 2 - Large break - AREVA Evaluation Model: 1919°F Surry Units 1 and 2 - Small break - Westinghouse Evaluation Model: 1845°F Surry Units 1 and 2 - Large break - Westinghouse Evaluation Model: 2095°F 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. Independently, as described in our letter dated July 31, 2007 (Serial No. 06-0936B), Dominion previously committed to perform a full Best Estimate-LBLOCA reanalysis for Surry Units 1 and 2 and submit the reanalysis results to the NRC by December 31,2008.

This information satisfies the 2007 annual reporting requirements of 10 CFR 50.46(a)(3)(ii).

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

v~Jt14~

Gerald T. Bischof ~

Vice President - Nuclear Engineering Dominion Energy Kewaunee, Inc.

Dominion Nuclear Connecticut, Inc.

Virginia Electric and Power Company

Serial No. 08-0348 Annual 50.46 ECCS Model Changes Docket Nos.: 50-305, 336/423, 338/339, 280/281 Page 3 of4 Commitments made in this letter: None Attachments: (5)

1. Report of Changes in Westinghouse and AREVA ECCS Evaluation Models.
2. 2007 Annual Reporting of 10 CFR 50.46 Margin Utilization - Kewaunee Power Station.
3. 2007 Annual Reporting of 10 CFR 50.46 Margin Utilization - Millstone Power Station Units 2 and 3.
4. 2007 Annual Reporting of 10 CFR 50.46 Margin Utilization - North Anna Power Station Units 1 and 2.
5. 2007 Annual Reporting 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 Sam Nunn Atlanta Federal Center 61 Forsyth Street, SW Suite 23T85 Atlanta, Georgia 30303 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 No. 08-0348 Annual 50.46 ECCS Model Changes Docket Nos.: 50-305, 336/423, 338/339, 280/281 Page 4 of 4 cc: (continued)

Mr. J. S. Cushing NRC Project Manager - Kewaunee 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 - Millstone Units 2 and 3 U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 83 11555 Rockville Pike Rockville, MD 20852-2738 Mr. S. P. Lingam NRC Project Manager - Surry and North Anna U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 G9A 11555 Rockville Pike Rockville, Maryland 20852

Serial Number 08-0348 Docket Nos. 50-305/336/423/338/339/280/281 ATTACHMENT 1 2007 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCSl 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 08-0348 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 1 of 5 REPORT OF CHANGES IN WESTINGHOUSE AND AREVA ECCS EVALUATION MODELS Kewaunee Power Station

1. Westinghouse identified the following changes and errors applicable to the KPS 1999 Westinghouse Best Estimate LBLOCA Evaluation Model (BE LBLOCA EM) with application to PWRs with upper plenum injection:
  • Revised Upper Plenum Volume Inputs
  • Errors in Reactor Vessel Nozzle Data Collections
  • Lower Plenum Unheated Conductors These items were evaluated to have a O°F impact on PCT.
2. Westinghouse identified the following changes and errors applicable to the KPS 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Nozzle Data Collections
  • Pump Weir Resistance Modeling
  • General Code Maintenance These items were evaluated to have a O°F impact on PCT.
3. Westinghouse identified an error in the fuel relocation model in the HOTSPOT code. This error applies to the KPS 1999 Westinghouse BE LBLOCA EM, with application to PWRs with upper plenum injection. In the axial node where burst is predicted to occur, a fuel relocation model in HOTSPOT is used to account for the likelihood that additional fuel pellet fragments above that elevation may settle into the burst region. It was discovered that the effect of fuel relocation on local linear heat rate was being calculated, but then cancelled out later in the coding.

A HOTSPOT reanalysis using the corrected code version resulted in an increase in the BE LBLOCA PCT of 10°F.

Millstone Power Station Unit 2

1. AREVA did not identify any changes or errors in the Realistic LBLOCA (RLBLOCA) and SBLOCA analyses for the 2007 calendar year.
2. In a notification dated March 3, 2008, AREVA identified a legacy FORTRAN programming issue with the point kinetics solution of the RELAP5-based computer codes. A programming error was made during the development of RELAP5 when the point kinetics package was installed, ca. 1980. The error consists of incorrect indexing in the four summations that compute terms for the delayed neutron fractions from each group that contributes to total power. The error adds an additional term to each of the summations. In most cases, the

Serial Number 08-0348 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 2 of 5 additional term seems to be much smaller than the legitimate terms in the summation so there has been negligible effect on the sum. The change in fission power, as well as total power, is less than 0.2%. The effect of the error was not discernable on the test problems used for the implementation testing; consequently the error was not detected. This error affects all versions of RELAP5 based computer programs. RELAP4 is not impacted by this error.

AREVA determined that the impact of this programming error is an 8aF decrease in the PCT for the MPS2 SBLOCA analysis.

Millstone Power Station Unit 3

1. Westinghouse identified the following changes and errors applicable to the MPS3 1981 Westinghouse LBLOCA Evaluation Model with BASH:
  • BASH Pellet Volumetric Heat Generation Rate
  • Errors in Reactor Vessel Nozzle Data Collections
  • LOCBART Specific Heat Model for Optimized ZIRLO' Cladding
  • Pump Weir Resistance Modeling
  • General Code Maintenance
  • LOCBART Oxide-to-Metal Ratio These items were evaluated to have a OaF impact on PCT.
2. Westinghouse identified the following changes and errors applicable to the MPS3 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Nozzle Data Collections
  • Pump Weir Resistance Modeling
  • General Code Maintenance These items were evaluated to have a oaF impact on PCT.
3. Westinghouse modified the LOCBART code to correct an inverted term in the calculation of the pellet volumetric heat generation rate. The LOCBART code is one of several computer codes used in the BASH LBLOCA Evaluation model for MPS3. This change affects the steady-state and transient heat generation for the hot rod and hot assembly, and could result in either an increase or decrease in PCT for a given calculation. Westinghouse determined that the LOCBART Pellet Volumetric Heat Generation Rate assessment for Millstone Unit 3 was

+39°F using the difference between the PCTs from LOCBART calculations with and without the error correction.

Serial Number 08-0348 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 3 of 5 North Anna Power Station Units 1 and 2

1. Westinghouse identified the following changes and errors applicable to the NAPS 1 and 2 1981 Westinghouse LBLOCA Evaluation Model with BASH:
  • BASH Pellet Volumetric Heat Generation Rate
  • Errors in Reactor Vessel Nozzle Data Collections
  • LOCBART Specific Heat Model for Optimized ZIRLO' Cladding
  • Pump Weir Resistance Modeling
  • General Code Maintenance
  • LOCBART Oxide-to-Metal Ratio These items were evaluated to have a OaF impact on PCT.
2. Westinghouse identified the following changes and errors applicable to the NAPS 1 and 2 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Nozzle Data Collections
  • Pump Weir Resistance Modeling
  • General Code Maintenance These items were evaluated to have a OaF impact on PCT.
3. Westinghouse modified the LOCBART code to correct an inverted term in the calculation of the pellet volumetric heat generation rate. The LOCBART code is one of several computer codes used in the BASH LBLOCA Evaluation model for NAPS 1 and 2. This change affects the steady-state and transient heat generation for the hot rod and hot assembly, and could result in either an increase or decrease in PCT for a given calculation. Westinghouse determined that a bounding value for the LOCBART Pellet Volumetric Heat Generation Rate assessment was +45°F based on non-plant specific sensitivity calculations.

Since Westinghouse is not the holder of the BASH LBLOCA analysis for NAPS 1 and 2, Dominion elected to apply the bounding value from available non-plant-specific sensitivity calculations (+45°F) for NAPS 1 and 2. This change is only applicable to the Westinghouse fuel.

4. AREVA identified a mixture level model limitation in the S-RELAP5 code. This error affects the AREVA RLBLOCA Evaluation Model which is used to analyze the LBLOCA for the AREVA fuel in NAPS 1 and 2. The S-RELAP5 mixture level model detection logic determines the locations of mixture level by primarily looking at the void distributions in stacks of consecutive vertical volumes. Under certain circumstances, the removal of extra mixture levels according to heat structure conditions may not be performed properly, resulting in random removal of mixture levels. This issue can arise in the AREVA RLBLOCA methodology where level tracking is important in stacked volumes such as the downcomer. As

Serial Number 08-0348 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 4 of 5 a result, AREVA has performed code modifications to fix this logic error in S-RELAP5 in order to eliminate potential level tracking problems. AREVA evaluated the impact of this correction as a change in PCT of -29°F for NAPS 1 and -19°F for NAPS 2.

5. AREVA identified a legacy FORTRAN programming issue with the point kinetics solution of the RELAP5-based computer codes. This error affects both the AREVA RLBLOCA Evaluation Model and the AREVA SBLOCA Evaluation Model which are used to analyze the LBLOCA and SBLOCA for the AREVA fuel in NAPS 1 and 2. A programming error was made during the development of RELAP5 when the point kinetics package was installed, ca. 1980. The error consists of incorrect indexing in the four summations that compute terms for the delayed neutron fractions from each group that contributes to total power. The error adds an additional term to each of the summations. In most cases, the additional term seems to be much smaller than the legitimate terms in the summation so there has been negligible effect on the sum. The change in fission power, as well as total power, is less than 0.2%. The effect of the error was not discernable on the test problems used for the implementation testing; consequently the error was not detected. This error affects all versions of RELAP5 based computer programs. AREVA determined that the impact of this programming error is an 8°F decrease in the PCT for the NAPS 1 and 2 SBLOCA analyses and a 20°F decrease in the PCT for the NAPS 1 and 2 RLBLOCA analyses.

Surry Power Station Units 1 and 2

1. Westinghouse identified the following changes and errors applicable to the SPS 1 and 2 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Nozzle Data Collections
  • Pump Weir Resistance Modeling
  • General Code Maintenance These items were evaluated to have a O°F impact on PCT.
2. Westinghouse identified the following changes and errors applicable to the SPS 1 and 2 2004 Westinghouse Best Estimate (BE) LBLOCA Evaluation Model Using ASTRUM:
  • Sampling of the Integrated Power Fraction in the Lower Third Section of the Core (PBOT) and Integrated Power Fraction in the Mid Third Section of the Core (PMID)
  • Errors in Reactor Vessel Nozzle Data Collections These items were evaluated to have a O°F impact on PCT.

Serial Number 08-0348 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 5 of 5

3. Westinghouse identified an error in the fuel relocation model in the HOTSPOT code. This error applies to the SPS 2004 Westinghouse BE-LBLOCA Evaluation Model Using ASTRUM. In the axial node where burst is predicted to occur, a fuel relocation model in HOTSPOT is used to account for the likelihood that additional fuel pellet fragments above that elevation may settle into the burst region. It was discovered that the effect of fuel relocation on local linear heat rate was being calculated, but then cancelled out later in the coding. A HOTSPOT reanalysis using the corrected code version resulted in an increase in the BE-LBLOCA PCT (of 51°F) from 2044°F to 2095°F. Discussion of this computer code error was provided to the NRC in a letter dated July 31, 2007 (Serial No. 06-0936B). The results of this evaluation were reviewed and accepted by the NRC in a letter dated September 6, 2007, issuing Licensing Amendments 254/253 (TAC Nos.

MD3609 and MD3610). Our letter dated July 31,2007 also committed to perform a full BE-LBLOCA reanalysis for Surry Units 1 and 2 and submit the reanalysis results to the NRC by December 31,2008.

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.

This information satisfies the 2007 annual reporting requirements of 10 CFR 50.46(a)(3)(ii).

Serial Number 08-0348 Docket No. 50-305 ATTACHMENT 2 2007 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2007 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION

Serial Number 08-0348 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 Tavg 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 Clad Temp COF)

LICENSING BASIS Analysis of Record PCT 1030 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. NOTRUMP Bubble Rise/Drift Flux Model Inconsistency 35 Corrections
2. NOTRUMP-EM Refined Break Spectrum o B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1065

Serial Number 08-0348 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 FQ: 2.5 FdH: 1.8 Fuel: 422 Vantage + SGTP(%): 10 Notes: Uprate to 1772 MWt. Effective beginning Cycle 26 Clad Temp (OF)

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

A. Prior ECCS Model Assessments

1. Revised Slowdown Heatup Uncertainty Distribution 5
2. Spacer Grid Heat Transfer Model Inputs 5
3. Inconsistent Vessel Vertical Level Modeling 0
4. Revised Downcomer Gap Inputs -59
5. Core Support Column Heat Slab Discrepancy 0 B. Planned Plant Modification Evaluations
1. None o
c. 2007 ECCS Model Assessments
1. HOTSPOT Fuel Relocation Error 10 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2045

Serial Number 08-0348 Docket Nos. 50-336/423 ATTACHMENT 3 2007 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2007 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 2 AND 3

Serial Number 08-0348 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 COF)

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 B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -8 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1778

Serial Number 08-0348 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 B. Planned Plant Modification Evaluations
1. Containment Sump Modification and Replacement PZR 2 C. 2007 ECCS Model Assessments
1. None 0 D. Other
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1825

Serial Number 08-0348 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: 3 Inches Analysis Date: 04/04 Vendor: Westinghouse FQ: 2.6 FAH: 1.7 Fuel: RFA/Vantage 5H SGTP (%): 10 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1009 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. NOTRUMP Bubble Rise 1 Drift Flux Model Inconsistency Corrections o
2. NOTRUMP-EM Refined Break Spectrum o B. Planned Plant Modification Evaluations
1. CHG/SI Alternate MiniFlow o C. 2007 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1009

Serial Number 08-0348 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: BASH Limiting Break Size: Cd=0.6 Analysis Date: 08/90 Vendor: Westinghouse FQ: 2.6 FAH: 1.7 Fuel: Vantage 5H SGTP (%): 10 Notes: VH5/RFA Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1974 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. BASH Minimum and Maximum Time Step Sizes 44 B. Planned Plant Modification Evaluations
1. CHG/SI Alternate MiniFlow o C. 2007 ECCS Model Assessments
1. LOCBART Pellet Volumetric Heat Generation Rate 39 D. Other
1. Rebaseline of AOR 30 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2087

Serial Number 08-0348 Docket Nos. 50-338/339 ATTACHMENT 4 2007 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2007 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 1 of 8 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name: North Anna Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: NOTRUMP Limiting Break Size: 3 Inches Analysis Date: 1995 Vendor: Westinghouse FQ: 2.32 FL\H: 1.65 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1704 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. NOTRUMP Specific Enthalpy Error 20
2. SALIBRARY Double Precision Error -15
3. Fuel Rod Initialization Error 10
4. Loop Seal Elevation Error -44
5. NOTRUMP-Mixture Level Tracking Errors 13
6. Removal of Part Length CRDMs 1
7. NOTRUMP-Bubble Rise/Drift Flux Model Inconsistencies 35
8. NOTRUMP-EM Refined Break Spectrum 85 B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1809

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 2 of 8 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name: North Anna Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: BASH Limiting Break Size: Cd=O.4 Analysis Date: 2004 Vendor: Westinghouse FQ: 2.19 F~H: 1.55 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 2086 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. LOCBART Fluid Property Logic Issue o
2. BASH Minimum and Maximum Time Step Sizes o B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. LOCBART Pellet Volumetric Heat Generation Rate 45 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2131

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 3 of 8 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 Fa: 2.32 FAH: 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. None o B. Planned Plant Modification Evaluations
1. Revised Test Flow Curve for HHSI -24 C. 2007 ECCS Model Assessments
1. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -8 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1372

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 4 of 8 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 FQ: 2.32 FAH: 1.65 Fuel: Mixed SGTP (%): 12 NAIF/Advanced Mark-BW Notes: None 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. RLBLOCA Choked Flow Disposition -26
5. RLBLOCA Changes in Uncertainty Parameters 10 B. Planned Plant Modification Evaluations
1. Advanced Mark-BW Top Nozzle Modification 65 C. 2007 ECCS Model Assessments
1. Mixture Level Model Limitation in the S-RELAP5 Code -29
2. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -20 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1925

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 5 of 8 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name: North Anna Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analysis Information EM: NOTRUMP Limiting Break Size: 3 Inches Analysis Date: 1995 Vendor: Westinghouse FQ: 2.32 FL\H: 1.65 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1704 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. NOTRUMP Specific Enthalpy Error 20
2. SALIBRARY Double Precision Error -15
3. Fuel Rod Initialization Error 10
4. Loop Seal Elevation Error -44
5. Removal of Part Length CRDMs 1
6. NOTRUMP-Mixture Level Tracking Errors 13
7. NOTRUMP-Bubble Rise/Drift Flux Model Inconsistencies 35
8. NOTRUMP-EM Refined Break Spectrum 85 B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1809

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 6 of 8 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name: North Anna Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analysis Information EM: BASH Limiting Break Size: Cd=OA Analysis Date: 2004 Vendor: Westinghouse FQ: 2.19 FAH: 1.55 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 2086 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. LOCBART Fluid Property Logic Issue o
2. BASH Minimum and Maximum Time Step Sizes o B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. LOCBART Pellet Volumetric Heat Generation Rate 45 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2131

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 7 of 8 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 FLlH: 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. None o B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -8 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1362

Serial Number 08-0348 Docket No. 50-338/339 Attachment 4, Page 8 of 8 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 FAH: 1.65 Fuel: Mixed: SGTP (%): 12 NAIF/Advanced Mark-BW Notes: None 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 o
4. RLBLOCA Choked Flow Disposition 22
5. RLBLOCA Changes in Uncertainty Parameters 10 B. Planned Plant Modification Evaluations
1. Advanced Mark-BW Top Nozzle Modification 65 C. 2007 ECCS Model Assessments
1. Mixture Level Model Limitation in the S-RELAP5 Code -19
2. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -20 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1919

Serial Number 08-0348 Docket Nos. 50-280/281 ATTACHMENT 5 2007 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2007 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2

Serial Number 08-0348 Docket No. 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: 3 Inches Analysis Date: 1996 Vendor: Westinghouse FQ: 2.5 FAH: 1.7 Fuel: SIF SGTP (%): 15 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1717 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. NOTRUMP - Mixture Level Tracking Errors 13
2. Removal of Part Length CRDMs -15
3. NOTRUMP-Bubble Rise/Drift Flux Model Inconsistencies 35
4. NOTRUMP-EM Refined Break Spectrum 85 B. Planned Plant Modification Evaluations
1. Westinghouse IFBA Fuel Product Implementation 10 C. 2007 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1845

Serial Number 08-0348 Docket No. 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: 7/1/06 Vendor: Westinghouse FQ: 2.6 F~H: 1.7 Fuel: OFA SGTP (%): 15 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 2044 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. None o B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. HOTSPOT Fuel Relocation Error 51 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2095

Serial Number 08-0348 Docket No. 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: 3 Inches Analysis Date: 1996 Vendor: Westinghouse FQ: 2.5 FAH: 1.7 Fuel: SIF SGTP (%): 15 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1717 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. NOTRUMP - Mixture Level Tracking Errors 13
2. Removal of Part Length CRDMs -15
3. NOTRUMP-Bubble Rise/Drift Flux Model Inconsistencies 35
4. NOTRUMP-EM Refined Break Spectrum 85 B. Planned Plant Modification Evaluations
1. Westinghouse IFBA Fuel Product Implementation 10 C. 2007 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1845

Serial Number 08-0348 Docket No. 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: 7/1/06 Vendor: Westinghouse FQ: 2.6 FAH: 1.7 Fuel: OFA SGTP (%): 15 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 2044 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. None o B. Planned Plant Modification Evaluations
1. None o C. 2007 ECCS Model Assessments
1. HOTSPOT Fuel Relocation Error 51 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2095
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