ML091820272

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Submittal of 2008 Annual Report of Emergency Core Cooling System (ECCS) Model Changes Pursuant to the Requirements of 10 CFR 50.46
ML091820272
Person / Time
Site: Millstone, Kewaunee, Surry, North Anna  Dominion icon.png
Issue date: 06/30/2009
From: Price J
Dominion Energy Kewaunee, Dominion Nuclear Connecticut, Dominion Resources Services, Virginia Electric & Power Co (VEPCO)
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
09-404, FOIA/PA-2011-0115
Download: ML091820272 (31)
v • d • e


Text

Dominion Resources Services, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 Web Address: www.dom.com June 30, 2009 U.S. Nuclear Regulatory Commission Serial No.09-404 Attention: Document Control Desk NL&OS/ RO 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 2008 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) 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. The calculated peak cladding temperatures (PCT) for the SBLOCA and

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 Page 2 of 4 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: 1065°F Kewaunee - Large break - Westinghouse Evaluation Model: 2045°F Millstone Unit 2 - Small break - AREVA Evaluation Model: 1714°F Millstone Unit 2 - Large break - AREVA Evaluation Model: 1825°F 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 - 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: 1395°F North Anna Unit 1 - Large break - AREVA Evaluation Model: 1893°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: 1338°F North Anna Unit 2 - Large break - AREVA Evaluation Model: 1887°F Surry Units 1 and 2 - Small break - Westinghouse Evaluation Model: 1845°F Surry Units 1 and 2 - Large break - Westinghouse Evaluation Model: 1857°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.

This information satisfies the 2008 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.

Very truly yours, J. J!\I n Price V'ce President - Nuclear Engineering D inion Energy Kewaunee, Inc.

Dominion Nuclear Connecticut, Inc.

Virginia Electric and Power Company

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 Page 3 of 4 Commitments made in this letter:

1. None.

Attachments: (5)

1) Report of Changes in Westinghouse and AREVA ECCS Evaluation Models.
2) 2008 Annual Report of 10 CFR 50.46 Margin Utilization - Kewaunee Power Station.
3) 2008 Annual Report of 10 CFR 50.46 Margin Utilization - Millstone Power Station Units 2 and 3.
4) 2008 Annual Report of 10 CFR 50.46 Margin Utilization - North Anna Power Station Units 1 and 2.
5) 2008 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 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

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 Page 4 of 4 cc: (continued)

NRC Senior Resident Inspector Surry Power Station Mr. P. S. Tam 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 B1A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. J. F. Stang, Jr.

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. D. N. Wright NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 0-8 H4A 11555 Rockville Pike Rockville, Maryland 20852-2738

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 ATTACHMENT 1 2008 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) 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 09-404 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 the following changes and errors applicable to the KPS 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Lower Plenum Surface Area Calculations
  • Discrepancy in Metal Masses Used From Drawings
  • General Code Maintenance These items were evaluated to have a OaF impact on PCT.
2. 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:
  • General Code Maintenance
  • HOTSPOT Burst Temperature Logic Errors These items were evaluated to have a OaF impact on peT.

Millstone Power Station (MPS) Unit 2

1. AREVA did not identify any additional changes or errors in the SBLOCA and LBLOCA analyses for the 2008 calendar year that were not previously reported in the 2007 Annual 10 CFR 50.46 report (letter dated June 26, 2008, Serial No. 08-0348).
2. In early 2009, AREVA evaluated the following change in the SBLOCA evaluation model for MPS2:

MPS2

~PCT Radiation to Fluid Heat Transfer Model Change -64°F This item was previously reported to the NRC in a letter dated June 18, 2009 (Serial No.09-375) to meet the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii).

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 2 of 4 Millstone Power Station (MPS) Unit 3

1. Westinghouse identified the following changes and errors applicable to the MPS 3 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Lower Plenum Surface Area Calculations
  • Discrepancy in Metal Masses Used From Drawings
  • General Code Maintenance These items were evaluated to have a OaF impact on PCT.
2. Westinghouse identified the following changes and errors applicable to the MPS 3 2004 Westinghouse Realistic Large Break LOCA Evaluation Model using the Automated Statistical Treatment of Uncertainty Method (ASTRUM):
  • General Code Maintenance
  • HOTSPOT Burst Temperature Logic Errors
  • CCFL Global Volume Error These items were evaluated to have a OaF impact on PCT.
3. In support of a Stretch Power Uprate (SPU), Westinghouse reanalyzed both,the SBLOCA with NOTRUMP and LBLOCA with ASTRUM. The reanalyses resulted in a SBLOCA PCT of 1193°F and a LBLOCA PCT of 1781°F. These results were approved by the NRC in the Safety Evaluation enclosed in a letter dated August 12, 2008 (TAC No. MD6070).

North Anna Power Station (NAPS) 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 and the 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP:
  • Errors in Reactor Vessel Lower Plenum Surface Area Calculations
  • Discrepancy in Metal Masses Used From Drawings
  • General Code Maintenance These items were evaluated to have a OaF impact on PCT.

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 3 of 4

2. AREVA evaluated the following changes in the SBLOCA evaluation models for NAPS 1 and 2:

NAPS1 NAPS2

~PCT ~PCT RCCA Reactivity Input -3°F -29°F Critical Flow Transition 26°F 5°F These items were previously reported to the NRC for NAPS 1 in a letter dated July 30, 2008 (Serial No. 08-0442) to meet the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii).

3. AREVA evaluated an issue related to the S-RELAP5 modeling of condensation in the cold legs and downcomer during the reflood phase of a large break LOCA.

AREVA determined that there is a OaF impact on the Realistic Large Break LOCA (RLBLOCA) analysis results for NAPS 1 and 2.

4. In early 2009, AREVA evaluated the following change in the RLBLOCA evaluation models for NAPS 1 and 2:

NAPS 1 and 2

~PCT Radiation to Fluid Heat Transfer Model Change -32°F This item was previously reported to the NRC in a letter dated May 4, 2009 (Serial No.09-263) to meet the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii).

Surry Power Station (SPS) 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 Lower Plenum Surface Area Calculations
  • Discrepancy in Metal Masses Used From Drawings
  • General Code Maintenance These items were evaluated to have a OaF impact on PCT.
2. Westinghouse identified the following changes and errors applicable to the SPS 1 and 2 2004 Westinghouse Realistic Large Break LOCA Evaluation Model using the Automated Statistical Treatment of Uncertainty Method (ASTRUM):
  • General Code Maintenance
  • HOTSPOT Burst Temperature Logic Errors These items were evaluated to have a OaF impact on PCT.

Serial Number 09-404 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1, Page 4 of 4

3. In a letter dated July 31, 2007 (Serial No. 06-936B), Dominion committed to perform a full Best-Estimate LBLOCA (BE-LBLOCA) reanalysis with ASTRUM for SPS 1 and 2 and to submit the reanalysis results to the NRC by December 31, 2008. The results of the reanalysis were submitted to the NRC in a letter dated December 17, 2008 (Serial No. 08-0739). The reanalysis resulted in a BE-LBLOCA PCT of 1857°F for SPS 1 and 2.
4. Westinghouse performed an evaluation to determine the impact of additional containment metal on the current licensing basis BE-LBLOCA analysis with ASTRUM. The evaluation resulted in a OaF impact on PCT for SPS 1 and 2.

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 2008 annual reporting requirements of 10 CFR 50.46(a)(3)(ii) and includes relevant 2009 changes reported to the NRC to date.

Serial Number 09-404 Docket No. 50-305 ATTACHMENT 2 2008 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2008 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION

Serial Number 09-404 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 Clad Temp (OF)

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. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 1065

Serial Number 09-404 Docket No. 50-305 Attachment 2, Page 2 of 2 10 CFR50.46 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 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
6. HOTSPOT Fuel Relocation Error 10 B. Planned Plant Modification Evaluations
1. None o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 2045

Serial Number 09-404 Docket Nos. 50-336/423 ATTACHMENT 3 2008 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2008 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 2 AND 3

Serial Number 09-404 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 B. Planned Plant Modification Evaluations

) 1. None o C. 2008 ECCS Model Assessments

1. Radiation to Fluid Heat Transfer Model Change -64*

D. Other

1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 1714
  • Reference submittal June 18, 2009 (Serial No.09-375)

Serial Number 09-404 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. 2008 ECCS Model Assessments
1. None 0 D. Other
1. None 0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1825

Serial Number 09-404 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 FAH: 1.65 Fuel: RFANantage 5H SGTP (%): 10 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record PCT 1193 PCT ASSESSMENTS (Delta PCT)

A. Prior ECCS Model Assessments

1. None o B. Planned Plant Modification Evaluations
1. None o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1193

Serial Number 09~404 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 FAH: 1.65 Fuel: RFA/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. None o B. Planned Plant Modification Evaluations
1. None o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1781

Serial Number 09-404 Docket Nos. 50-338/339 ATTACHMENT 4 2008 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2008 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2

Serial Number 09-404 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 FAH: 1.65 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record peT 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. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1809

Serial Number 09-404 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=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 0
2. BASH Minimum and Maximum Time Step Sizes 0
3. LOCBART Pellet Volumetric Heat Generation Rate 45 B. Planned Plant Modification Evaluations
1. None o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2131

Serial Number 09-404 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 FQ: 2.32 FL\H: 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 B. Planned Plant Modification Evaluations
1. Revised Test Flow Curve for HHSi -24 C. 2008 ECCS Model Assessments
1. RCCA Reactivity Input -3
2. Critical Flow Transition 26 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1395

Serial Number 09-404 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 0
4. RLBLOCA Choked Flow Disposition -26
5. RLBLOCA Changes in Uncertainty Parameters 10
6. Mixture Level Model Limitation in the S-RELAP5 Code -29
7. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -20 B. Planned Plant Modification Evaluations
1. Advanced Mark-BW Top Nozzle Modification 65 C. 2008 ECCS Model Assessments
1. Cold Leg Condensation Under Predicted by S-RELAP5 o
2. Radiation to Fluid Heat Transfer Model Change -32 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1893

Serial Number 09-404 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 FAH: 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. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1809

Serial Number 09-404 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 0
2. BASH Minimum and Maximum Time Step Sizes 0
3. LOCBART Pellet Volumetric Heat Generation Rate 45 B. Planned Plant Modification Evaluations
1. None o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 2131

Serial Number 09-404 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 FAH: 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 B. Planned Plant Modification Evaluations
1. None o C. 2008 ECCS Model Assessments
1. RCCA Reactivity Input -29
2. Critical Flow Transition 5 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1338

Serial Number 09-404 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 0
4. RLBLOCA Choked Flow Disposition 22
5. RLBLOCA Changes in Uncertainty Parameters 10
6. Mixture Level Model Limitation in the S-RELAP5 Code -19
7. Point Kinetics Programming Issue with RELAP5-Based Computer Codes -20 B. Planned Plant Modification Evaluations
1. Advanced Mark-BW Top Nozzle Modification 65 C. 2008 ECCS Model Assessments
1. Cold Leg Condensation Under Predicted by S-RELAP5 o
2. Radiation to Fluid Heat Transfer Model Change -32 D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1887

Serial Number 09-404 Docket Nos. 50-280/281 ATTACHMENT 5 2008 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2008 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2

Serial Number 09-404 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. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1845

Serial Number 09-404 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: 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. None o B. Planned Plant Modification Evaluations
1. Evaluation of Additional Containment Metal o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1857

Serial Number 09-404 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 FL\H: 1.7 Fuel: SIF SGTP (%): 15 Notes: None Clad Temp (OF)

LICENSING BASIS Analysis of Record peT 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. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1845

Serial Number 09-404 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: 11/3/08 Vendor: Westinghouse FQ: 2.5 FAH: 1.7 Fuel: OFA SGTP (0/0): 7 Notes: None Clad Temp (OF)

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

A. Prior ECCS Model Assessments

1. None o B. Planned Plant Modification Evaluations
1. Evaluation of Additional Containment Metal o C. 2008 ECCS Model Assessments
1. None o D. Other
1. None o LICENSING BASIS PCT + PCT ASSESSMENTS PCT = 1857
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