ML071840174
| ML071840174 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Kewaunee, Surry, North Anna  |
| Issue date: | 06/28/2007 |
| From: | Gerald Bichof Dominion Energy Kewaunee, Dominion Nuclear Connecticut, Dominion Resources Services, Virginia Electric & Power Co (VEPCO) |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 07-0464 | |
| Download: ML071840174 (33) | |
Text
Dominion Resources Services, Inc.
i 0 0 0 Dominion Boulevard, Glen Allcn. VA LiO(>O 1 Dominion*
Vl c b Addrcs: www.dom.com June 28, 2007 U.S. Nuclear Regulatory Commission Serial No. 07-0464 Attention: Document Control Desk NL&OSlGDM R1 Washington, DC 20555 Docket Nos. 50-305 50-3361423 50-3381339 50-2801281 License Nos. DPR-43 DPR-65lNPF-49 NPF-417 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 I AND 2 2006 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 Units 2 and 3 (MPS 2&3), North Anna Power Station Units 1 and 2 (NAPS 1&2), and Surry Power Station Units 1 and 2 (SPS 1&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&3, NAPS 1&2, and SPS 1&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&3, NAPS 1&2, and SPS 1&2 in Attachments 2, 3, 4 and 5, respectively. The NAPS 1&2 2006 cores were comprised of both Westinghouse fuel and AREVA fuel.
Therefore, there are two sets of margin utilization data for NAPS 1&2. The calculated peak cladding temperatures (PCT) for the SBLOCA and LBLOCA analyses for KPS, MPS 2&3, NAPS 1&2, and SPS 1&2 are summarized below.
Serial Number 07-0464 Docket Nos. 50-30513361423/338/339/280/281 Page 2 of 4 Kewaunee - Small break - Westinghouse Evaluation Model:
Kewaunee - Large break - Westinghouse Evaluation Model:
Millstone Unit 2 - Small break - AREVA Evaluation Model:
Millstone Unit 2 - Large break - AREVA Evaluation Model:
Millstone Unit 3 - Small break - Westinghouse Evaluation Model:
Millstone Unit 3 - Large break - Westinghouse Evaluation Model:
North Anna Unit 1 - Small break - Westinghouse Evaluation Model:
North Anna Unit 1 - Large break - Westinghouse Evaluation Model:
North Anna Unit 1 - Small break - AREVA Evaluation Model:
North Anna Unit I- Large break - AREVA Evaluation Model:
North Anna Unit 2 - Small break - Westinghouse Evaluation Model:
North Anna Unit 2 - Large break - Westinghouse Evaluation Model:
North Anna Unit 2 - Small break - AREVA Evaluation Model:
North Anna Unit 2 - Large break - AREVA Evaluation Model:
Surry Units 1 and 2 - Small break - Westinghouse Evaluation Model:
Surry Units 1 and 2 - Large break - Westinghouse Evaluation Model:
The LOCA results for KPS, MPS 2&3, NAPS 1&2, and SPS 1&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.
Regarding Surry's LBLOCA analysis, in a November 16, 2006 letter (Serial No.06-936)
Dominion submitted a revised best estimate LBLOCA analysis using the approved Westinghouse Automated Statistical Treatment of Uncertainty Method (ASTRUM) for NRC approval. Upon approval, this reanalysis will provide improved margin to the 2200°F limit for PCT specified in 10 CFR 50.46.
This information satisfies the 2006 annual reporting requirements of 10 CFR 50.46(a)(3)(ii).
If you have any further questions regarding this submittal, please contact Mr. Gary D. Miller at (804) 273-2771.
Very truly yours, Gerald T. Bischof C/
Vice President - Nuclear Engineering Commitments made in this letter: None
Serial Number 07-0464 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. 2006 Annual Reporting of 10 CFR 50.46 Margin Utilization - Kewaunee Power Station.
- 3. 2006 Annual Reporting of 10 CFR 50.46 Margin Utilization - Millstone Power Station Units 2 and 3.
- 4. 2006 Annual Reporting of 10 CFR 50.46 Margin Utilization - North Anna Power Station Units 1 and 2.
- 5. 2006 Annual Reporting of 10 CFR 50.46 Margin Utilization - Surry Power Station Units Iand 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 Ill 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 Mr. S. C. Burton NRC Senior Resident Inspector Kewaunee Power Station Mr. R. I. Treadway NRC Senior Resident lnspector Millstone Power Station
Serial Number 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 Page 4 of 4 Mr. J. T. Reece NRC Senior Resident Inspector North Anna Power Station Mr. E. Riggs NRC Senior Resident Inspector Surry Power Station Ms. M. H. Chernoff NRC Project Manager - Kewaunee Power Station U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08G9A Rockville, Maryland 20852-2738 Mr. J. D. Hughey NRC Project Manager - Millstone Power Station Units 2 and 3 U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08B3 Rockville, Maryland 20852-2738 Mr. S. P. Lingam NRC Project Manager - Surry Power Station U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08G9A Rockville, Maryland 20852 Mr. R. A. Jervey NRC Project Manager - North Anna Power Station U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 08G9A Rockville, Maryland 20852
Serial Number 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 ATTACHMENT I 2006 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 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1 REPORT OF CHANGES IN WESTINGHOUSE AND AREVA ECCS EVALUATION MODELS Generic Westinclhouse PCT Assessments with No Impact on PCT Westinghouse identified the following change applicable to the NOTRUMP Small Break Loss of Coolant Accident (SBLOCA) and BASH Large Break Loss of Coolant Accident (LBLOCA) evaluation models. The change was evaluated to have a PCT impact of 0°F. Since this item has no impact on PCT, it will not be shown on the PCT Margin Utilization sheets provided in Attachments 2 through 5.
- a. General Code Maintenance (BASHINOTRUMP)
Westinghouse identified the following change in the 1999 Westinghouse Best Estimate LBLOCA evaluation model (BE LBLOCA EM) with application to PWRs with upper plenum injection. This evaluation model is utilized at Kewaunee Power Station. The change was evaluated to have a PCT impact of 0°F. Since this item has no impact on PCT, it will not be shown on the PCT Margin Utilization sheet provided in Attachment 2.
- a. General Code Maintenance (1999 Westinghouse BE LBLOCA EM, Application to PWRs with Upper Plenum Injection)
The following summarizes the plant specific PCT assessments since the previous annual report.
Kewaunee Power Station During the course of reviewing several extended power uprate and replacement steam generator SBLOCA analyses, the Nuclear Regulatory Commission (NRC) questioned the break spectrum analyzed in the NOTRUMP EM. The NRC was concerned that the resolution of the break spectrum used in the NOTRUMP EM (15 , 2, 3, 4, and 6 inch cases) may not be fine enough to capture the worst break with regard to limiting PCT as per 10 CFR 50.46. That is, the plant could be SBLOCA limited with regard to overall LOCA results. In response to this, Westinghouse performed some preliminary work indicating that in some cases more limiting results could be obtained from non-integer break sizes; however, the magnitude of the impact was far less than that shown in preliminary work performed by the NRC. Based on this, 'Westinghouse performed evaluations to determine if all currently operating plants would maintain compliance with the 10 CFR 50.46 acceptance criteria when considering a refined SBLOCA break spectrum.
For plants with low SBLOCA PCTs (i.~!.,less than 1700°F) and overall SBLOCA results that are significantly non-limiting when compared with LBLOCA results, no explicit refined break spectrum calc;ulations were performed, leading to an estimated PCT impact of 0°F for 10 CFR 50.46 reporting purposes. Since KPS Page 1 of 6
Serial Number 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1 falls into this category of plants, the impact on PCT will be tracked as APCT =
0°F.
Westinghouse evaluated the following changes and errors in the Westinghouse BE LBLOCA EM for KPS:
KPS APCT Inconsistent Vessel Vertical Level Modeling I 0°F 1 Revised Downcomer Gap Inputs 1 -59°F I These items were previously reported to the NRC in a letter dated September 1, 2006 (Serial No.06-681) to meet the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii).
Westinghouse identified an error in the calculation of the core support column metal mass which results in a small discrepancy in the total lower plenum heat slab metal mass. This error applies to the KPS 1999 Westinghouse BE LBLOCA EM, with application to PWRs with Upper Plenum Injection. Westinghouse evaluated the corrected metal mass for the core support column for impact on the current LBLOCA licensing basis analysis. The difference in the metal mass is very small and produces a negligible effect on the LBLOCA analysis, leading to an estimated PCT impact of 0°F.
Millstone Power Station Unit 2
- 1. AREVA, during a review of the vessel model for the S-RELAP5 SBLOCA analysis for MPS2, showed that the upper tie plate (UTP) flow area was not being used in the CCFL model at the core exit. The UTP flow area is the minimum flow area at the top of the core and should be used by the CCFL model to obtain accurate velocities. AREVA corrected the UTP flow area and flow path options in the CCFL model. The updated S-RELAP5 SBLOCA calculation yielded an estimated PCT impact of APCT = -22°F.
- 2. AREVA, in the process of converting S-RELAP5 to FORTRAN-90, identified deviations in the calculated response. The deviations were traced to the use of array indices in the ICECON computer code that result in interpolations outside of the data table. The error involves the calculation of steam condensation and was essentially undetectable with the F77 compiler. With the F90 compiler and execution, the spurious use of data outside the data table was more noticeable.
Investigation of the interpolation error also identified several minor errors associated with calculation of the limits of the steam condensation rate.
Page 21 of 6
Serial Number 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1 The same errors exist in the version of ICECON used in the RFPAC computer code, which is part of the SEMIPWR-98 LBLOCA methodology. AREVA evaluated the PCT impact of these errors to be APCT = 0°F for dry containment plants and determined that this PCT assessment is applicable to the MPS2 LBLOCA analysis.
- 3. AREVA provided an evaluation to assess the impact on the MPS2 LBLOCA PCT resulting from the containment sump modification and replacement pressurizer at MPS2. The containment sump modification is being made to address the GSI-191 issue. The additional heat structures from the containment sump modification and replacement pressurizer resulted in an increase in the MPS2 LBLOCA results of APCT = 2°F.
Millstone Power Station Unit 3
- 1. During the course of reviewing several extended power uprate and replacement steam generator SBLOCA analyses, the Nuclear Regulatory Commission (NRC) questioned the break spectrum analyzed in the NOTRUMP EM. The NRC was concerned that the resolution of the break spectrum used in the NOTRUMP EM (1.5, 2, 3, 4, and 6 inch cases) may not be fine enough to capture the worst break with regard to limiting PCT as per 10 CFR 50.46. That is, the plant could be SBLOCA limited with regard to overall LOCA results. In response to this, Westinghouse performed some preliminary work indicating that in some cases more limiting results could be obtained from non-integer break sizes; however, the magnitude of the impact was far less than that shown in preliminary work performed by the NRC. Based on this, Westinghouse performed evaluations to determine if all currently operating plants would maintain compliance with the 10 CFR 50.46 acceptance criteria when considering a refined SBLOCA break spectrum.
For plants with low SBLOCA PCTs (i.e., less than 1700°F) and overall SBLOCA results that are significantly non-limiting when compared with LBLOCA results, no explicit refined break spectrum calculations were performed, leading to an estimated PCT impact of 0°F for 10 CFR 50.46 reporting purposes. Since MPS3 falls into this category of plants, the impact on PCT, resulting from the NOTRUMP-EM Refined Break Spectrum issue, will be tracked as APCT = 0°F.
- 2. Westinghouse evaluated the following change in the BASH LBLOCA evaluation model for MPS3:
BASH Minimum and Maximum Time Step Sizes Page 3 of 6
Serial Number 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1 This item was previously reported to the NRC in a letter dated November 20, 2006 (Serial No.06-981) to meet the 30-day reporting requirements of 10 CFR 50.46 (a)(3)(ii)
- 3. Westinghouse identified an issue whereby a recent BASH LBLOCA evaluation predicted an increase in PCT for Integral Fuel Burnable Absorber (IFBA) fuel that was attributed primarily to the use of fuel rod initial conditions based on PAD Version 4.0. This result called into question the basis for forward-fit implementation of PAD Version 4.0, and existing IFBA analyses based on PAD Version 3.4 were reviewed to identify conditions that could lead to similar behavior.
MPS3 is unaffected by this issue since the MPS3 BASH LBLOCA analysis was evaluated previously using fuel rod initial conditions based on PAD Version 4.0.
- 4. Westinghouse provided a re-evaluation of a charging pump alternate mini-flow line modification, which was installed during the spring 2007 Refueling Outage (3R11).
As a result of the charging pump alternate mini-flow line modification, revised charginglsafety injection (CHGISI) system flows were developed and an evaluation was performed to determine the impact of the revised flows on the current LBLOCA and SBLOCA analyses-of-record (AORs). The revised flows were determined to have a negligible effect on the MPS3 SBLOCA and LBLOCA transients. The CHGISI Alternate MiniFlow modification will be tracked as a APCT
= 0°F impact for both the MPS3 SBLOCA and LBLOCA analyses.
North Anna Power Station Units 1 and 2
- 1. Westinghouse evaluated the following change in the NOTRUMP SBLOCA evaluation model for North Anna Units 1 and 2:
NAPS1&2 APCT I NOTRUMP-EM Refined Break Spectrum I 85°F This item was previously reported to the NRC in a letter dated March 22, 2007 (Serial No. 07-0142) to meet the 30-day reporting requirements of 10 CFR 50.46 (a)(3)(ii).
Westinghouse reviewed some recent BASH-EM LBLOCA sensitivity calculations, which led to a recommendation to reduce the minimum and maximum time step sizes in BASH during reflood. Sensitivity calculations using BASH and SMUUTH show that reducing the minimum and maximum time step sizes in BASH during reflood results in either a negligible change or a modest increase in the integral flooding rate for most cases, leading to an estimated impact of APCT = 0°F for 10 CFR 50.46 reporting purposes.
Page 4 of 6
Serial Number 07-0464 Docket Nos. 50-305/336/423/338/339/280/281 Attachment 1
- 3. Westinghouse identified an issue whereby a recent BASH LBLOCA evaluation predicted an increase in PCT for Integral Fuel Burnable Absorber (IFBA) fuel that was attributed primarily to the use of fuel rod initial conditions based on PAD Version 4.0. This result called into question the basis for forward-fit implementation of PAD Version 4.0, and existing IFBA analyses based on PAD Version 3.4 were reviewed to identify conditions that could lead to similar behavior. NAPS 1 & 2 are unaffected by this issue since the NAPS 1 & 2 BASH LBLOCA analyses were evaluated previously using fuel rod initial conditions based on PAD Version 4.0.
- 4. AREVA did not identify any new changes or errors in the Realistic LBLOCA (RLBLOCA) and SBLOCA analyses that were not previously reported to the NRC in the 2005 Annual 10 CFR 50.46 letter dated June 28,2006 (Serial No.06-521).
Surw Power Station Units 1 and 2 Westinghouse evaluated the following change in the NOTRUMP SBLOCA evaluation model for Surry Units 1 and 2:
SPS1&2 APCT 1 NOTRUMP-EM Refined Break Spectrum I 85°F I This item was previously reported to the NRC in a letter dated March 22, 2007 (Serial No. 07-0142) to meet the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii).
Westinghouse reviewed some recent BASH-EM LBLOCA sensitivity calculations, which led to a recommendation to reduce the minimum and maximum time step sizes in BASH during reflood. Sensitivity calculations using BASH and SMUUTH show that reducing the minimum and maximum time step sizes in BASH during reflood results in either a negligible change or a modest increase in the integral flooding rate for most cases, leading to an estimated impact of APCT = 0°F for 10 CFR 50.46 reporting purposes.
Westinghouse identified an issue whereby a recent BASH LBLOCA evaluation predicted an increase in PCT for Integral Fuel Burnable Absorber (IFBA) fuel that was attributed primarily to the use of fuel rod initial conditions based on PAD Version 4.0. This result called into question the basis for forward-fit implementation of PAD Version 4.0, and existing IFBA analyses based on PAD Version 3.4 were reviewed to identify conditions that could lead to similar behavior. SPS 1 & 2 are unaffected by this issue since the SPS 1 & 2 BASH LBLOCA analyses were evaluated previously using fuel rod initial conditions based on PAD Version 4.0.
Page 5 of 6
Serial Number 07-0464 Docket Nos. 50-3051336/4231338/339/2801281 Attachment 1 Conclusion The LOCA results for KPS, MPS 2&3, NAPS 1&2, and SPS 1&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 2006 annual reporting requirements of 10 CFR 50.46(a)(3)(ii).
Page 6 of 6
Serial Number 07-0464 Docket No. 50-305 ATTACHMENT 2 2006 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2006 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION
Serial Number 07-0464 Docket No. 50-305 Attachment 2 10 CFR 50.46 MARGIN UTILIZATION SMALL BREAK LOCA Plant Name: Kewaunee Power Station Utility Name: Dominion Energv Kewaunee, Inc.
Analysis Information EM: NOTRUMP Limiting Break Size: 3 Inch CL, High Tav Analysis Date: 05114/02 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 RiseIDrift Flux Model Inconsistency 35 Corrections B. Planned Plant Modification Evaluations
- 1. None C. 2006 ECCS Model Assessments
- 1. NOTRUMP-EM Refined Break Spectrum D. Other
Serial Number 07-0464 Docket No. 50-305 Attachment 2 10 CFR 50.46 MARGIN UTILIZATION LARGE BREAK LOCA Plant Name: Kewaunee Power Station Utility Name: Dominion Energy Kewaunee, Inc.
Analvsis Information EM: UP1 (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 Blowdown Heatup Uncertainty Distribution 5
- 2. Spacer Grid Heat Transfer Model Inputs 5 B. Planned Plant Modification Evaluations
- 1. None C. 2006 ECCS Model Assessments
- 1. Inconsistent Vessel Vertical Level Modeling
- 2. Revised Downcomer Gap Inputs
- 3. Core Support Column Heat Slab Discrepancy D. Other
Serial Number 07-0464 Docket Nos. 50-3361423 ATTACHMENT 3 2006 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2006 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3
Serial Number 07-0464 Docket Nos. 50-3361423 Attachment 3 10 CFR 50.46 MARGIN UTILIZATION SMALL BREAK LOCA Plant Name: Millstone Power Station, Unit 2 Utility Name: Dominion Nuclear Connecticut, Inc.
Analvsis Information EM: PWR Small Break LOCA, Limiting Break Size: 0.08 ft2 S-RELAP5 Based Analysis Date: 0I102 Vendor: AREVA Peak Linear Power: 15.1 kWlft 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
- 2. Revised SBLOCA Guideline B. Planned Plant Modification Evaluations
- 1. None C. 2006 ECCS Model Assessments
- 1. Core Exit Modeling-Upper Tie Plate Flow Area D. Other
Serial Number 07-0464 Docket Nos. 50-3361423 Attachment 3 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: SEMIPWR-98 Limiting Break Size: 1.0 DECLG Analysis Date: 11/98 Vendor: AREVA Peak Linear Power: 15.1 kW/ft Notes: None Clad Temp ( O F )
LICENSING BASIS Analysis of Record PCT 1814 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments Corrected Corrosion Enhancement Factor ICECON Coding Errors Setting RFPAC Fuel Temperatures at Start of Reflood SISPNCHIujun98 Code Error Error in Flow Blockage Model in TOODEE2 Change in TOODEE2-Calculation of QMAX Change in Gadolinia Modeling PWR LBLOCA Split Break Modeling TEOBY Calculation Error Inappropriate Heat Transfer in TOODEE2 End-of-Bypass Prediction by TEOBY R4SS Overwrite of Junction lnertia lncorrect Junction lnertia Multipliers Errors Discovered During RODEX2 V&V Error in Broken Loop SG Tube Exit Junction Inertia RFPAC Refill and Reflood Calculation Code Errors lncorrect Pump Junction Area Used in RELAP4 Error in TOODEE2 Clad Thermal Expansion Accumulator Line Loss Error Inconsistent Loss Coefficients Used for Robinson LBLOCA Pump Head Adjustment for Pressure Balance Initialization B. Planned Plant Modification Evaluations
- 1. ICECON Code Errors D. Other
Serial Number 07-0464 Docket Nos. 50-3361423 Attachment 3 40 CFR 50.46 MARGIN UTILIZATION SMALL BREAK LOCA Plant Name: Millstone Power Station, Unit 3 Utility Name: Dominion Nuclear Connecticut, Inc.
Analvsis Information EM: NOTRUMP Limiting Break Size: 3 Inches Analysis Date: 04/04 Vendor: Westinghouse FQ: 2.6 FAH: 1.7 Fuel: RFANantage 5H SGTP (%): 10 Notes: None Clad Temp ( O F )
LICENSING BASIS Analysis of Record PCT 1009 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections B. Planned Plant Modification Evaluations
- 1. CHGISI Alternate MiniFlow C. 2006 ECCS Model Assessments
- 1. NOTRUMP-EM Refined Break Spectrum D. Other
Serial Number 07-0464 Docket Nos. 50-3361423 Attachment 3 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: VH5IRFA Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1974 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. None B. Planned Plant Modification Evaluations
- 1. CHGISI Alternate MiniFlow C. 2006 ECCS Model Assessments
- 1. BASH Minimum and Maximum 'Time Step Sizes 44 D. Other
Serial Number 07-0464 Docket Nos. 50-3381339 ATTACHMENT 4 2006 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2006 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2
Serial Number 07-0464 Docket No. 50-3381339 Attachment 4 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 Analvsis Information EM: NOTRUMP Limiting Break Size: 3 Inches Analysis Date: 1995 Vendor: Westing house FQ: 2.32 F:AH: 1.65 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1704 PCT ASSESSMENTS (Delta PCT)
Prior ECCS Model Assessments
- 1. NOTRUMP Specific Enthalpy Error
- 2. SALIBRARY Double Precision Error
- 3. Fuel Rod Initialization Error
- 4. Loop Seal Elevation Error
- 5. NOTRUMP-Mixture Level Tracking Errors
- 6. Removal of Part Length CRDMs
- 7. NOTRUMP-Bubble RiseIDrift Flux Model Inconsistencies Planned Plant Modification Evaluations
- 1. None 2006 ECCS Model Assessments
- 1. NOTRUMP-EM Refined Break Spectrum Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 4 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name: North Anna Power Station, Unit 1 Utility Name: Virginia Electric and Power Companv Analysis Information EM: BASH Limiting Break Size: Cd=0.4 Analysis Date: 2004 Vendor: Westing house FQ: 2.19 FAH: 1.55 Fuel: NAIF SGTP (%): 7 Notes: None Clad Temp ( O F )
LICENSING BASIS Analysis of Record PCT 2086 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. LOCBART Fluid Property Logic Issue B. Planned Plant Modification Evaluations
- 1. None C. 2006 ECCS Model Assessments
- 1. BASH Minimum and Maximum Time Step Sizes D. Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 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 Analvsis Information EM: AREVA SB EM Limiting Break Size: 5.2 Inches (SI Line)
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 1404 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. None B. Planned Plant Modification Evaluations
- 1. Revised Test Flow Curve for HtiSI C. 2006 ECCS Model Assessments
- 1. None D. Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 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 Analvsis Information EM: AREVA RLBLOCA EM Limiting Break Size: DEGB Analysis Date: 2004 Vendor: AREVA FQ: 2.32 FAH: 1.65 Fuel: Mixed SGTP (%): 12 Advanced Mark-BW Notes: None Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT I853 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. Forslund-Rohsenow Correlation Modeling 64
- 2. RWST Temperature Assumption 8
- 3. LBLOCAISeismic SG Tube Collapse 0
- 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. 2006 ECCS Model Assessments
- 1. None D. Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 4 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 Analvsis Information EM: NOTRUMP Limiting Break Size: 3 Inches Analysis Date: 1995 Vendor: Westing house FQ: 2.32 FAH: 1.65 Fuel: NAlF SGTP (%): 7 Notes: None Clad Temp ( O F )
LICENSING BASIS Analysis of Record PCT 1704 PCT ASSESSMENTS (Delta PCT)
Prior ECCS Model Assessments
- 1. NOTRUMP Specific Enthalpy Error 20
- 2. SALIBRARY Double Precision Iirror -15
- 3. Fuel Rod Initialization Error 10
- 4. Loop Seal Elevation Error -44
- 5. Removal of Part Length CRDM:: 1
- 6. NOTRUMP-Mixture Level Tracking Errors 13
- 7. NOTRUMP-Bubble RiseIDrift Flux Model Inconsistencies 35 Planned Plant Modification Evaluations
- 1. None 2006 ECCS Model Assessments
- 1. NOTRUMP-EM Refined Break :Spectrum Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 4 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 Analvsis Information EM: BASH Limiting Break Size: Cd=0.4 Analysis Date: 2004 Vendor: Westing house 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 B. Planned Plant Modification Evaluations
- 1. None C. 2006 ECCS Model Assessments
- 1. BASH Minimum and Maximum Time Step Sizes D. Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 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 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. None B. Planned Plant Modification Evaluations
- 1. None C. 2006 ECCS Model Assessments
- 1. None D. Other
Serial Number 07-0464 Docket No. 50-3381339 Attachment 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 FAH: 1.65 Fuel: Mixed: SGTP (%): 12 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 Correlatior~Modeling
- 2. RWST Temperature Assumption
- 3. LBLOCAISeismic SG Tube Collapse
- 4. RLBLOCA Choked Flow Disposition
- 5. RLBLOCA Changes in Uncertainty Parameters B. Planned Plant Modification Evaluations
- 1. Advanced Mark-BW Top Nozzle Modification 65 C. 2006 ECCS Model Assessments
- 1. None D. Other
Serial Number 07-0464 Docket Nos. 50-2801281 ATTACHMENT 5 2006 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2006 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2
Serial Number 07-0464 Docket Nos. 50-2801281 Attachment 5 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name: Surry Power Station, Unit I 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 ( O F )
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 RiseIDrift Flux Model Inconsistencies 35 B. Planned Plant Modification Evaluations
- 1. Westinghouse IFBA Fuel Product Implementation 10 C. 2006 ECCS Model Assessments
- 1. NOTRUMP-EM Refined Break Spectrum D. Other
Serial Number 07-0464 Docket Nos. 50-2801281 Attachment 5 I 0 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name: Surry Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM: BASH Limiting Break Size: Cd=0.4 Analysis Date: 2001 Vendor: Westinghouse FQ: 2.32 FAH: 1.62 Fuel: SIF SGTP (%): 15 Notes: None Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 21 I 7 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. LBLOCAlSeismic SG Tube Collapse
- 2. BASH-EM Transient Terminatioln
- 3. LOCBART Fluid Property Logic Issue
- 4. LOCBART ZlRLOTM Cladding Specific Heat Model Error
- 5. PAD 4.0 Initial Pellet Temperatures
- 6. Removal of Part-Length CRDMs
- 7. Pressurizer Surge Line Piping Schedule Reconciliation
- 8. LOCBART Fluid Property Logic Issue-Augmented
- 9. Revised Containment Heat Sink Input
- 10. Revised Containment Spray Flowrate
- 11. Revised Containment Free Volume
- 12. LOCBART Fluid Property Logic Issue-Augmented B. Planned Plant Modification Evaluations
- 1. Westinghouse IFBA Fuel Produ~ctImplementation 41 C. 2006 ECCS Model Assessments
- 1. BASH Minimum and Maximum Time Step Sizes 0 D. Other
Serial Number 07-0464 Docket Nos. 50-2801281 Attachment 5 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name: Surry Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analvsis Information EM: NOTRUMP Limiting Break Size: 3 Inches Analysis Date: 1996 Vendor: Westing house 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 RiseIDrift Flux Model Inconsistencies 35 B. Planned Plant Modification Evaluations
- 1. Westinghouse IFBA Fuel Product Implementation 10 C. 2006 ECCS Model Assessments
- 1. NOTRUMP-EM Refined Break !Spectrum D. Other
Serial Number 07-0464 Docket Nos. 50-2801281 Attachment 5 10 CFR 50.46 MARGIN UTILIZATION WESTINGHOUSE LARGE BREAK LOCA Plant Name: Surry Power Station, Unit 2 Utility Name: Virginia Electric and Power Company Analvsis Information EM: BASH Limiting Break Size: Cd=0.4 Analysis Date: 2001 Vendor: Westing house FQ: 2.32 FAH: 1.62 Fuel: SIF SGTP (%): 15 Notes: None Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 21 I 7 PCT ASSESSMENTS (Delta PCT)
A. Prior ECCS Model Assessments
- 1. LBLOCNSeismic SG Tube Collapse
- 2. BASH-EM Transient Terminatioln
- 3. LOCBART Fluid Property Logic Issue
- 4. LOCBART ZlRLOTM Cladding Specific Heat Model Error
- 5. PAD 4.0 Initial Pellet Temperatures
- 6. Removal of Part-Length CRDMs
- 7. Pressurizer Surge Line Piping Schedule Reconciliation
- 8. LOCBART Fluid Property Logic Issue-Augmented
- 9. Revised Containment Heat Sink Input
- 10. Revised Containment Spray Flawrate
- 11. Revised Containment Free Volume
- 12. LOCBART Fluid Property Logic Issue-Augmented B. Planned Plant Modification Evaluations
- 1. Westinghouse IFBA Fuel Produ~ctImplementation 41 C. 2006 ECCS Model Assessments
- 1. BASH Minimum and Maximum Time Step Sizes D. Other