ML111800499
| ML111800499 | |
| Person / Time | |
|---|---|
| Site: | Millstone, Kewaunee, Surry, North Anna  (DPR-032, DPR-037, DPR-043, DPR-065, NPF-004, NPF-007, NPF-049) |
| Issue date: | 06/27/2011 |
| 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 | |
| 11-331 | |
| Download: ML111800499 (28) | |
Text
Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Boulevard, 25E, Glen Allen, VA 23060 June 27, 2011 u.s. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.
NL&OS/
Docket Nos.
License Nos.11-331 RO 50-305 50-336/423 50-338/339 50-280/281 DPR-43 DPR-65/NPF-49 NPF-4/7 DPR-32/37 DOMINION ENERGY KEWAUNEE, INC.
DOMINION NUCLEAR CONNECTICUT, INC..
YIRGINIA ELECTRIC AND POWER COMPANY KEWAUNEE POWER STATION MILLSTONE POWER STATION UNITS 2 AND 3
~ORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 2010 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM ECCS MODEL I HANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 I~ accordance with 10 CFR 50.46(a)(3)(ii), Dominion Energy Kewaunee, Inc. (DEK),
[pominion Nuclear Connecticut, Inc. (DNC) and Virginia Electric and Power Company (iDominion) hereby submit the annual summary of permanent changes to the emergency gore cooling system (ECCS) evaluation models for Kewaunee Power Station (KPS),
~illstone Power Station (MPS) Units 2 and 3, North Anna Power Station (NAPS) Units 1 qnd 2, and Surry Power Station (SPS) Units 1 and 2, respectively.
I, 4ttachment 1 of this letter provides a report describing plant-specific evaluation model
~hanges associated with the Westinghouse and AREVA Small Break Loss of Coolant 1'ccident (SBLOCA) and Large Break Loss of Coolant Accident (LBLOCA) ECCS 8
1 valuation models for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2.
I~formation 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,
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281 Page 2 of 4 respectively. The calculated peak cladding temperatures (PCT) for the SBLOCA and LBLOCA analyses for KPS, MPS 2 and 3, NAPS 1 and 2, and SPS 1 and 2 are summarized below.
Kewaunee - Small break - Westinghouse Evaluation Model:
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 - AREVA Evaluation Model:
North Anna Unit 1 - Large break - AREVA 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:
1065°F 2045°F 1718°F 1845°F 1193°F 1781°F 1395°F 1862°F 1338°F 1874°F 2012°F 185rF 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 2010 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, Commitments made in this letter: None.
Serial Number 11-331 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) 2010 Annual Reporting of 10 CFR 50.46 Margin Utilization - Kewaunee Power Station.
- 3) 2010 Annual Reporting of 10 CFR 50.46 Margin Utilization - Millstone Power Station Units 2 and 3.
- 4) 2010 Annual Reporting of 10 CFR 50.46 Margin Utilization - North Anna Power Station Units 1 and 2.
- 5) 2010 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 Marquis One Tower - Suite '1200 245 Peachtree Center Avenue, N.E., Suite 1200 Atlanta, Georgia 30303-12S7 U.S. Nuclear Regulatory Commission Region III 2443 Warrenville Road Suite 210 Lisle, Illinois 60532-4352 NRC Senior Resident Inspector Kewaunee Power Station NRC Senior Resident Inspector Millstone Power Station NRC Senior Resident Inspector North Anna Power Station NRC Senior Resident Inspector Surry Power Station
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281 Page 4 of 4 Mr. K. D. Feintuch 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 MaiI Stop 0-8 B3 11555 Rockville Pike Rockville, MD 20852-2738 Mr. R. E. Martin NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Ms. K. R. Cotton NRC Project Manager U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 G-9A 11555 Rockville Pike Rockville, Maryland 20852-2738 Mr. J. E. Reasor, Jr.
Old Dominion Electric Cooperative Innsbrook Corporate Center, Suite 300 4201 Dominion Blvd.
Glen Allen, Virginia 23060
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281 ATTACHMENT 1 2010 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 11-331 Docket Nos. 50-305/336/423/338/339/280/281, 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 affecting the 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP for KPS.
General Code Maintenance.
The code maintenance activities performed in 2010 did not impact predicted PCT.
Urania-Gadolinia Pellet Thermal Conductivity Calculation.
Two errors were discovered in the pellet thermal conductivity calculation for urania-gadolinia pellets in the SBLOCTA code. First, the calculation did not include the terms required to adjust for pellet densities other than 95% of the theoretical density. Second, the conversion from Fahrenheit to Rankine used an adder of 459 instead of 459.67. These errors have been corrected and evaluated for impact on existing Small Break LOCA analysis results. This item was evaluated to have a O°F impact on PCT for SBLOCA.
Pellet Crack and Dish Volume Calculation.
Two errors were discovered in the calculation of the normalized pellet crack and dish volumes in the SBLOCTA code.
First, an incorrect operator was used to select between two tables of normalized volume vs. linear heat generation rate. Second, the normalized volume at 18 kW/ft was incorrectly programmed in one of the tables as 1.58 instead of 1.59. These errors have been corrected in the SBLOCTA code and will be corrected (where applicable) in future versions of the BASH and LOCBART codes.
This item was evaluated to have a 0 0 F impact on PCT for SBLOCA.
Treatment of Vessel Average Temperature Uncertainty. Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only u_"
instrument uncertainties, corresponding to the indicated temperature being lower than the actual temperature.
This uncertainty was then applied as a u+/_" uncertainty in some LOCA analyses, rather than using specific U+" and u_" uncertainties.
This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results. This item was evaluated to have a 0 0 F impact on PCT for SBLOCA.
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:
Treatment of Vessel Average Temperature Uncertainty. Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only u_"
instrument uncertainties, corresponding to the indicated temperature being lower than the actual temperature.
This uncertainty was then applied as a u+/_" uncertainty in some LOCA analyses, rather than using specific U+" and u_" uncertainties.
This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results. This item was evaluated to have a O°F impact on PCT for LBLOCA.
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281, Page 2 of 5 Treatment of Interfacial Drag Multipliers in Upper Plenum Injection Plants.
For Upper Plenum Injection (UPI) plants, condensation and interfacial drag multipliers which affect the simulated draining of the upper plenum are modeled within WCOBRAfTRAC. The interfacial drag multipliers are applied in the upper plenum and the Counter-Current Flow Limitation (CCFL) region of the vessel. For some licensing-basis analyses, these multipliers were not ranged as intended. This item was evaluated to have a 0° F impact on PCT for LBLOCA.
Millstone Power Station Unit 2 1.
AREVA identified no changes or errors affecting the S-RELAP5 based Small Break LOCA Evaluation Model for MPS 2.
2.
AREVA identified the following changes and errors applicable to the SEM/PWR-98 evaluation model for LBLOCA for MPS 2.
Notification of an Array Index issue in the RELAP4 code which is used as part of the SEM/PWR-98 LBLOCA Evaluation Methodology. The Array IREMV is dimensioned to 10 but was being re-initialized to zero out to 20 within the code. This was impacting the first 10 values of the ITP array which contains flags indicating the type of choking. This item was evaluated to have a 0° F impact on PCT for LBLOCA.
Millstone Power Station Unit 3 1.
Westinghouse identified the following changes and errors to the 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP.
General Code Maintenance.
The code maintenance activities performed in 2010 did not impact predicted PCT.
Urania-Gadolinia Pellet Thermal Conductivity Calculation. Two errors were discovered in the pellet thermal conductivity calculation for urania-gadolinia pellets in the SBLOCTA code. First, the calculation did not include the terms required to adjust for pellet densities other than 95% of the theoretical density. Second, the conversion from Fahrenheit to Rankine used an adder of 459 instead of 459.67. These errors have been corrected and evaluated for impact on existing Small Break LOCA analysis results. This item was evaluated to have a 0° F impact on PCT for SBLOCA.
Pellet Crack and Dish Volume Calculation.
Two errors were discovered in the calculation of the normalized pellet crack and dish volumes in the SBLOCTA code.
First, an incorrect operator was used to select between two tables of normalized volume vs. linear heat generation rate. Second, the normalized volume at 18 kW/ft was incorrectly programmed in one of the tables as 1.58 instead of 1.59.
This item was evaluated to have a O°F impact on PCT for SBLOCA.
Treatment of Vessel Average Temperature Uncertainty.
Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only "-"
instrument uncertainties, corresponding to the indicated temperature being lower than
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281, Page 3 of 5 the actual temperature.
This uncertainty was then applied as a "+/-" uncertainty in some LOCA analyses, rather than using specific "+" and "-" uncertainties.
This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results. This item was'evaluated to have a 0° F impact on PCT for SBLOCA.
2.
Westinghouse identified the following changes and errors applicable to the 2004 Westinghouse Best Estimate Large Break LOCA Evaluation Model using the Automated Statistical Treatment of Uncertainty Method (ASTRUM) for MPS3:
Treatment of Vessel Average Temperature Uncertainty. Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only "-"
instrument uncertainties, corresponding to the indicated temperature being lower than the actual temperature.
This uncertainty was then applied as a "+/-" uncertainty in some LOCA analyses, rather than using specific "+" and "-" uncertainties.
This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results. This item was evaluated to have a 0° F impact on PCT for LBLOCA.
North Anna Power Station Units 1 and 2 1.
AREVA identified no changes or errors in the SBLOCA evaluation models for North Anna Units 1 and 2:
2.
AREVA identified the following changes and errors applicable to the Realistic LBLOCA, RELAP5 based evaluation model for North Anna Units 1 and 2.
Steam Generator Entrainment Bias Factor (FIJ) Change. An internal AREVA corrective action item was written to evaluate the impact of not entraining the appropriate amount of liquid into the steam generator tubes during a LBLOCA event. The Realistic Large Break LOCA (RLBLOCA) methodology uses a bias on interphase friction at the steam generator tube sheet entrance to ensure an acceptable amount of liquid is entrained into the steam generator tubes during a large break. The bias determination was performed by comparing calculated results from SRELAP5 with measured data from the Upper Plenum Test Facility (UPTF) Tests. The UPTF facility represents a full scale, four loop PWR complete with the necessary hardware that can be used to represent geometry specific phenomena that occurs during a large or small break LOCA. The S-RELAP5 parameter that controls entrainment is interphase friction. The range of interphase friction spans several orders of magnitude between the flow regimes occurring in the hot leg, hot leg riser, steam generator inlet plenum and steam generator tube sheet. Consequently, determining the uncertainty in interphase friction is not feasible so a conservative bias is used instead. The magnitude of the bias is determined by adjusting the S-RELAP5 RLBLOCA Multiplier FIJ until S-RELAP5 over-predicts the entrainment observed in UPTF Tests by an arbitrary amount. The FIJ multiplier of 1.75 under-predicts the measured entrainment and is therefore invalid.
Re-evaluation of the S-RELAP5 entrainment yielded a value of 5.0 for the FIJ multiplier, which is appropriate with a modeling change to the steam generator riser angle, greater than 30 degrees, and with the horizontal stratification flag set to off in the hot leg. The corrections for this error were implemented and the PCT impact to North Anna Units 1 and 2 is assessed to be - 4°F.
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281, Page 4 of 5 For North Anna Unit 2, this item was previously reported to the NRC in a letter dated July 29,2010 (Serial No.10-440) to meet the 30-day reporting requirements of 10 CFR 50.46(a)(3)(ii).
Surry Power Station Units 1 and 2 1.
Westinghouse identified the following changes and errors applicable to the 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP for SPS.
General Code Maintenance.
The code maintenance activities performed in 2010 did not impact predicted PCT.
Urania-Gadolinia Pellet Thermal Conductivity Calculation. Two errors were discovered in the pellet thermal conductivity calculation for urania-gadolinia pellets in the SBLOCTA code. First, the calculation did not include the terms required to adjust for pellet densities other than 95% of the theoretical density. Second, the conversion from Fahrenheit to Rankine used an adder of 459 instead of 459.67. These errors have been corrected and evaluated for impact on existing Small Break LOCA analysis results. This item was evaluated to have a O°F impact on PCT for SBLOCA.
Pellet Crack and Dish Volume Calculation.
Two errors were discovered in the calculation of the normalized pellet crack and dish volumes in the SBLOCTA code.
First, an incorrect operator was used to select between two tables of normalized volume vs. linear heat generation rate. Second, the normalized volume at 18 kW/ft was incorrectly programmed in one of the tables as 1.58 instead of 1.59.
This item was evaluated to have a 0°F impact on PCT for SBLOCA.
Treatment of Vessel Average Temperature Uncertainty. Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only "-"
instrument uncertainties, corresponding to the indicated temperature being lower than the actual temperature.
This uncertainty was then applied as a "+/-" uncertainty in some LOCA analyses, rather than using specific "+" and "-" uncertainties.
This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results. This item was evaluated to have a 0° F impact on PCT for SBLOCA.
2.
Westinghouse identified the following changes and errors applicable to the 2004 Westinghouse Best Estimate Large Break LOCA Evaluation Model using the Automated Statistical Treatment of Uncertainty Method (ASTRUM) for SPS 1 and 2:
Treatment of Vessel Average Temperature Uncertainty. Historically, the overall vessel average temperature uncertainty calculated by Westinghouse considered only "-"
instrument uncertainties, corresponding to the indicated temperature being lower than the actual temperature.
This uncertainty was then applied as a "+/-" uncertainty in some LOCA analyses, rather than using specific "+" and "-" uncertainties.
This discrepancy has been evaluated for impact on existing Large and Small Break LOCA analysis results. This item was evaluated to have a 0° F impact on PCT for LBLOCA.
Serial Number 11-331 Docket Nos. 50-305/336/423/338/339/280/281, Page 5 of 5 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 annual reporting requirements of 10 CFR 50.46(a)(3)(ii) covering calendar year 2010.
Serial Number 11-331 Docket No. 50-305 ATTACHMENT 2 2010 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2010 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY KEWAUNEE, INC.
KEWAUNEE POWER STATION
Serial Number 11-331 Docket No. 50-305, Page 1 of 2 10 CFR 50.46 MARGIN UTILIZATION* SMALL BREAK LOCA Plant Name:
Kewaunee Power Station Utility Name:
Dominion Energy Kewaunee, Inc.
Analysis Information EM:
NOTRUMP Limiting Break Size:
3 Inch Cl, High Tav Analysis Date:
05/14/02 Vendor:
Westinghouse FQ:
2.5 FdH:
1.8 Fuel:
422 Vantage +
SGTP(%):
10 Notes:
Uprate to 1772 MWt. Effective beginning Cycle 26 LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments Clad Temp (OF) 1030 1.
Reactor Coolant Pump Reference Conditions 0
2.
Pressurizer Fluid Volumes 0
3.
lower Guide Tube Assembly Weight 0
4.
Discrepancy in NOTRUMP REST Draindown Calculation 0
5.
NOTRUMP Bubble Rise/Drift Flux Model 35 Inconsistency Corrections 6.
NOTRUMP-EM Refined Break Spectrum 0
7.
Errors in Reactor Vessel Nozzle Data Collections 0
8.
Pump Weir Resistance Modeling 0
9.
Errors in Reactor Vessel lower Plenum Surface 0
Area Calculations 10.
Discrepancy in Metal Masses Used from Drawings 0
B.
C.
D.
Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
Urania-Gadolinia Pellet Thermal Conductivity Calculation 2.
Pellet Crack and Dish Volume Calculation 3.
Treatment of Vessel Average Temperature Uncertainty Other 1.
None o
o o
o o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1065
Serial Number 11-331 Docket No. 50-305, Page 2 of 2 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name:
Utility Name:
Kewaunee Power Station Dominion Energy Kewaunee, Inc.
Limiting Break Size:
Split Analysis Information EM:
UPI (1999)
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 LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
Clad Temp COF) 2084 A.
B.
C.
D.
Prior ECCS Model Assessments 1.
Pressurizer Fluid Volumes 2.
Vessel Unheated Conductor Noding 3.
Level Boundary Selection 4.
Containment Relative Humidity Assumption 5.
Diffuser Plate Modeling 6.
Downcomer Momentum Area 7.
Revised Blowdown Heatup Uncertainty Distribution 8.
Spacer Grid Heat Transfer Model Inputs 9.
Inconsistent Vessel Vertical Level Modeling 10.
Revised Downcomer Gap Inputs 11.
Core Support Column Heat Slab Discrepancy 12.
HOTSPOT Fuel Relocation Error 13.
Revised Upper Plenum Volume Inputs 14.
Steam Generator Nozzle Volume Accounting Error 15.
Errors in Reactor Vessel Nozzle Data Collections 16.
Lower Plenum Unheated Conductors 17.
HOTSPOT Burst Temperature Logic Errors 18.
Discrepancy in Metal Masses Used From Drawings (Lower Support Plate) 19.
HOTSPOT Gap Heat Transfer Logic 20.
HOTSPOT Statistical Output Logic Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
Treatment of Vessel Average Temperature Uncertainty 2.
Treatment of Interfacial Drag Multipliers in Upper Plenum Injection Plants Other 1.
None oo o
o o
o 5
5 o
-59 o
10 o
o o
ooo oo o
oo o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT=
2045
Serial Number 11-331 Docket Nos. 50-336/423 ATTACHMENT 3 2010 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2010 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION NUCLEAR CONNECTICUT, INC.
MILLSTONE POWER STATION UNITS 2 AND 3
Serial Number 11-331 Docket Nos. 50-336/423, 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:
S-RELAP5 Based Analysis Date:
01/02 Vendor:
AREVA Peak Linear Power:15.1 kW/ft Notes:
None 2
0.08 ft LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
Clad Temp COF) 1941 A.
B.
C.
D.
Prior ECCS Model Assessments 1.
Decay Heat Model Error 2.
Revised SBLOCA Guideline 3.
Core Exit Modeling-Upper Tie Plate Flow Area 4.
Point Kinetics Programming Issue with RELAP5-Based Computer Codes 5.
S-RELAP5 Choked Flow Error with Non-Condensables Present 6.
Radiation to Fluid Heat Transfer Model Change 7.
RELAP5 Kinetics and Heat Conduction Model 8.
RODEX2 Thermal Conductivity Degradation Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
None Other 1.
None
-133 o
-22
-8 o
-64 4
o o
o o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1718
1814 Serial Number 11-331 Docket Nos. 50-336/423, 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 kW1ft Notes:
None Clad Temp COF)
LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
Corrected Corrosion Enhancement Factor
-1 2.
ICECON Coding Errors 0
3.
Setting RFPAC Fuel Temperatures at Start of Reflood
-2 4.
SISPNCH/ujun98 Code Error 0
5.
Error in Flow Blockage Model in TOODEE2 0
6.
Change in TOODEE2-Calculation of QMAX 0
7.
Change in Gadolinia Modeling 0
8.
PWR LBLOCA Split Break Modeling 0
9.
TEOBY Calculation Error 0
10.
Inappropriate Heat Transfer in TOODEE2 0
11.
End-of-Bypass Prediction by TEOBY 0
12.
R4SS Overwrite of Junction Inertia 0
13.
Incorrect Junction Inertia Multipliers 1
14.
Errors Discovered During RODEX2 V&V 0
15.
Error in Broken Loop SG Tube Exit Junction Inertia 0
16.
RFPAC Refill and Reflood Calculation Code Errors 16 17.
Incorrect Pump Junction Area Used in RELAP4 0
18.
Error in TOODEE2 Clad Thermal Expansion
-1 19.
Accumulator Line Loss Error
-1 20.
Inconsistent Loss Coefficients Used for Robinson LBLOCA 0
21.
Pump Head Adjustment for Pressure Balance Initialization
-3 22.
ICECON Code Errors 0
23 Containment Sump Modification and Replacement PZR 2
24.
Non-Conservative RODEX Fuel Pellet Temperature 20 B.
Planned Plant Modification Evaluations 1.
None o
C.
2010 ECCS Model Assessments 1.
Array Index Issues in the RELAP4 Code D.
Other 1.
None LICENSING BASIS PCT + PCT ASSESSMENTS o
o PCT=
1845
Serial Number 11-331 Docket Nos. 50-336/423, 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.
Limiting Break Size:
4 Inches Analysis Information EM:
NOTRUMP Analysis Date:
02/07/07 Vendor:
Westinghouse FQ:
2.6 Fuel:
RFA-2 Notes:
None FAH:
SGTP (%):
1.65 10 Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1193 PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
Errors in Reactor Vessel Lower Plenum Surface Area Calculations 0
2.
Discrepancy in Metal Masses Used From Drawings 0
B.
C.
D.
Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
Urania-Gadolinia Pellet Thermal Conductivity Calculation 2.
Pellet Crack and Dish Volume Calculation 3.
Treatment of Vessel Average Temperature Uncertainty Other 1.
None o
ooo o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1193
Serial Number 11-331 Docket Nos. 50-336/423, 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.
Limiting Break Size:
Guillotine Analysis Information EM:
ASTRUM (2004)
Analysis Date:
04/17/07 Vendor:
Westinghouse FQ:
2.6 Fuel:
RFA-2 Notes:
None F~H:
SGTP (%):
1.65 10 Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1781 PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
HOTSPOT Burst Temperature Logic Errors 0
2.
CCFL Global Volume Error 0
3.
HOTSPOT Gap Heat Transfer Logic 0
4.
Discrepancy in Metal Masses Used From Drawings 0
5.
Error in ASTRUM Processing of Average Rod Burnup 0
and Rod Internal Pressure B.
C.
D.
Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
Treatment of Vessel Average Temperature Uncertainty 2.
Error in ASTRUM Processing of Average Rod Burnup Other 1.
None o
o o
o LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1781
Serial Number 11-331 Docket Nos. 50-338/339 ATTACHMENT 4 2010 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2010 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2
Serial Number 11-331 Docket Nos. 50-338/339, Page 1 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA SMALL BREAK LOCA Plant Name:
North Anna Power Station, Unit 1 Utility Name:
Virginia Electric and Power Company Analysis Information EM:
AREVA SB EM Limiting Break Size:
5.2 Inches (SI Line)
Analysis Date:
2004 Vendor:
AREVA FQ:
2.32 FAH:
1.65 Fuel:
Advanced Mark-BW SGTP (%):
7 Notes:
None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
Point Kinetics Programming Issue with RELAP5-Based Computer Codes 2.
RCCA Reactivity Input 3.
Critical Flow Transition 4.
RELAP5 Kinetics and Heat Conduction Model 5.
TAC03 - Thermal Conductivity Degradation Clad Temp (OF) 1404
-8
-3 26 oo B.
C.
D.
Planned Plant Modification Evaluations 1.
Revised Test Flow Curve for HHSI 2.
Advanced Mark BW Top Nozzle Modification 2010 ECCS Model Assessments 1.
None Other 1.
None
-24 o
o o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1395
Serial Number 11-331 Docket Nos. 50-338/339, Page 2 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA LARGE BREAK LOCA Plant Name:
North Anna Power Station, Unit 1 Utility Name: Virginia Electric and Power Company Analysis Information EM:
AREVA RLBLOCA EM Limiting Break Size:
DEGB Analysis Date:
2004 Vendor:
AREVA FQ:
2.32 FilH:
1.65 Fuel:
Mixed:
SGTP (%):
12 NAIF/Advanced Mark-BW Notes:
Only AREVA Fuel in Core, Analysis Bounds Both LICENSING BASIS Analysis of Record PCT Clad Temp (OF) 1853 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.
ICECON Code Errors 0
5.
RLBLOCA Choked Flow Disposition
-26 6.
RLBLOCA Changes in Uncertainty Parameters 10 7.
Blowdown Quench 0
8.
Mixture Level Model Limitation in the S-RELAP5 Code
-29 9.
Point Kinetics Programming Issue
-20 with RELAP5-Based Computer Codes 10.
Cold Leg Condensation Under Predicted by 0
S-RELAP5 11.
Cross-Flow Junction Area in S-RELAP 0
Model 12.
Radiation to Fluid Heat Transfer Model Change
-32 13.
S-RELAP5 Kinetics and Heat Conduction Model
-29 14.
RODEX3A - Thermal Conductivity Degradation 0
B.
Planned Plant Modification Evaluations 1.
Advanced Mark-BW Top Nozzle Modification 2.
GSI-191 Sump Strainer 3.
MUR Implementation 65 o
2 C.
2010 ECCS Model Assessments 1.
Steam Generator Entrainment Bias Factor (FIJ) Change
-4 D.
Other 1.
None 0
LICENSING BASIS PCT + PCT ASSESSMENTS.
PCT =
1862
Serial Number 11-331 Docket Nos. 50-338/339, Page 3 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA SMALL BREAK LOCA Plant Name:
North Anna Power Station, Unit 2 Utility Name:
Virginia Electric and Power Company Analysis Information EM:
AREVA SB EM Limiting Break Size:
3 Inches Analysis Date:
2004 Vendor:
AREVA FQ:
2.32 F~H:
1.65 Fuel:
Advanced Mark-BW SGTP (%):
7 Notes:
None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
Point Kinetics Programming Issue with RELAP5-Based Computer Codes 2.
RCCA Reactivity Input 3.
Critical Flow Transition 4.
RELAP5 Kinetics and Heat Conduction Model 5.
TAC03 - Thermal Conductivity Degradation Clad Temp (OF) 1370
-8
-29 5oo B.
C.
D.
Planned Plant Modification Evaluations 1.
Advanced Mark BW Top Nozzle Modification 2010 ECCS Model Assessments 1.
None Other 1.
None o
o o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1338
Serial Number 11-331 Docket Nos. 50-338/339, Page 4 of 4 10 CFR 50.46 MARGIN UTILIZATION - AREVA LARGE BREAK LOCA Plant Name:
North Anna Power Station, Unit 2 Utility Name: Virginia EIE?ctric and Power Company Analysis Information EM:
AREVA RLBLOCA EM Limiting Break Size:
DEGB Analysis Date:
2004 Vendor:
AREVA FQ:
2.32 FilH:
1.65 Fuel:
Mixed:
SGTP (%):
12 NAIF/Advanced Mark-BW Notes:
Only AREVA Fuel in Core, Analysis Bounds Both Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1789 PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
Forslund-Rohsenow Correlation Modeling 64 2.
RWST Temperature Assumption 8
3.
LBLOCNSeismic SG Tube Collapse 0
4.
ICECON Code Errors 0
5.
RLBLOCA Choked Flow Disposition 22 6.
RLBLOCA Changes in Uncertainty Parameters 10 7.
Mixture Level Model Limitation in the S-RELAP5 Code
-19 8.
Point Kinetics Programming Issue
-20 with RELAP5-Based Computer Codes 9.
Cold Leg Condensation Under Predicted by S-RELAP5 0
10.
Cross-Flow Junction Area in S-RELAP Model 0
11.
Radiation to Fluid Heat Transfer Model Change
-32 12.
S-RELAP5 Kinetics and Heat Conduction Model
-29 13.
RODEX3A - Thermal Conductivity Degradation 0
B.
C.
D.
Planned Plant Modification Evaluations 1.
Advanced Mark-BW Top Nozzle Modification 2.
GSI-191 Sump Strainer 3.
MUR Implementation 2010 ECCS Model Assessments 1.
Steam Generator Entrainment Bias Factor (FIJ) Change Other 1.
None 65 o
20
-4 o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1874
Serial Number 10-331 Docket Nos. 50-280/281 ATTACHMENT 5 2010 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM fECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2010 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2
Serial Number 11-331 Docket Nos. 50-280/281, 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 Limiting Break Size:
2.75 Inches Analysis Information EM:
NOTRUMP Analysis Date:
5/7/2009 Vendor:
Westinghouse FQ:
2.5 Fuel:
SIF Notes:
None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
None FL\\H:
SGTP (%):
1.7 7
Clad Temp (OF) 2012 o
B.
C.
D.
Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
Urania-Gadolinia Pellet Thermal Conductivity Calculation 2.
Pellet Crack and Dish Volume Calculation 3.
Treatment of Vessel Average Temperature Uncertainty Other 1.
None o
o oo o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
2012
Serial Number 11-331 Docket Nos. 50-280/281, 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 Limiting Break Size:
DEG Analysis Information EM:
ASTRUM (2004)
Analysis Date:
11/3/08 Vendor:
Westinghouse FQ:
2.5 Fuel:
OFA Notes:
None FAH:
SGTP (%):
1.7 7
Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1857 PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
HOTSPOT Burst Temperature Logic Errors 0
2.
Error in ASTRUM Processing of Average Rod Burnup 0
and Rod Internal Pressure 3.
Discrepancy in Metal Masses Used From Drawings 0
4.
HOTSPOT Gap Heat Transfer Logic 0
B.
C.
D.
Planned Plant Modification Evaluations 1.
Evaluation of Additional Containment Metal 2010 ECCS Model Assessments 1.
Treatment of Vessel Average Temperature Uncertainty Other 1.
None o
o o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1857
Serial Number 11-331 Docket Nos. 50-280/281, 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 Limiting Break Size:
2.75 Inches Analysis Information EM:
NOTRUMP Analysis Date:
5/7/2009 Vendor:
Westinghouse FQ:
2.5 Fuel:
SIF Notes:
None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
None FAH:
SGTP (%):
1.7 7
Clad Temp (OF) 2012 o
B.
C.
D.
Planned Plant Modification Evaluations 1.
None 2010 ECCS Model Assessments 1.
Urania-Gadolinia Pellet Thermal Conductivity Calculation 2.
Pellet Crack and Dish Volume Calculation 3.
Treatment of Vessel Average Temperature Uncertainty Other 1.
None o
ooo o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
2012
Serial Number 11-331 Docket Nos. 50-280/281, 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 Limiting Break Size:
DEG Analysis Information EM:
ASTRUM (2004)
Analysis Date:
11/3/08 Vendor:
Westinghouse FQ:
2.5 Fuel:
OFA Notes:
None F8H:
SGTP (%):
1.7 7
Clad Temp (OF)
LICENSING BASIS Analysis of Record PCT 1857 PCT ASSESSMENTS (Delta PCT)
A.
Prior ECCS Model Assessments 1.
HOTSPOT Burst Temperature Logic Errors 0
2.
Error in ASTRUM Processing of Average Rod Burnup 0
and Rod Internal Pressure 3.
Discrepancy in Metal Masses Used From Drawings 0
4.
HOTSPOT Gap Heat Transfer Logic 0
B.
C.
D.
Planned Plant Modification Evaluations 1.
Evaluation of Additional Containment Metal 2010 ECCS Model Assessments 1.
Treatment of Vessel Average Temperature Uncertainty Other 1.
None o
o o
LICENSING BASIS PCT + PCT ASSESSMENTS PCT =
1857