Text

Submittal of 2019 Annual Report of Emergency Core Cooling System Model Changes Pursuant to the Requirements of 10 CFR 50.46
	ML20181A539
Person / Time
Site:	Millstone, Summer, Surry, North Anna
Issue date:	06/29/2020
From:	Mark D. Sartain; Dominion Energy Nuclear Connecticut, Dominion Energy South Carolina, Virginia Electric & Power Co (VEPCO)
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	20-219
	Download: ML20181A539 (44)
	v • d • e

June 29, 2020 Dominion Energy Services, Inc.

5000 Dominion Boulevard, Glen Allen, VA 23060 DominionEnergy.com i; Dominion

--' Energy 10 CFR 50.46 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Serial No.:

20-219 NRNGDM:

R1 Docket Nos.:

50-336/423 50-338/339 50-280/281 50-395 License Nos.:

DPR-65/NPF-49 DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

DOMINION ENERGY SOUTH CAROLINA, INC.

VIRGINIA ELECTRIC AND POWER COMPANY MILLSTONE POWER STATION UNITS 2 AND 3 NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 VIRGIL C. SUMMER NUCLEAR STATION UNIT 1 NPF-4/7 DPR-32/37 NPF-12 2019 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 In accordance with 10 CFR 50.46(a)(3)(ii), Dominion Energy Nuclear Connecticut, Inc.

(DENC), Virginia Electric and Power Company (Dominion Energy Virginia) and Dominion Energy South Carolina, Inc. (DESC) hereby submit the annual summary of permanent changes to the emergency core cooling system (ECCS) evaluation models (EMs) for Millstone Power Station (MPS) Units 2 and 3, North Anna Power Station (NAPS) Units 1 and 2, Surry Power Station (SPS) Units 1 and 2, and Virgil C. Summer Nuclear Station (VCS) Unit 1, respectively. of this letter provides a report describing plant-specific evaluation model changes associated with the Westinghouse and Framatome Small Break Loss of Coolant Accident (SBLOCA) and Large Break Loss of Coolant Accident (LBLOCA) ECCS EMs for MPS 2 and 3, NAPS 1 and 2, SPS 1 and 2, and VCS 1, as applicable.

Information regarding the effect of the ECCS EM changes upon the reported SBLOCA and LBLOCA analyses of record results is provided for MPS 2 and 3, NAPS 1 and 2, SPS 1 and 2, and VCS 1 in Attachments 2, 3, 4, and 5, respectively. The calculated peak cladding temperatures (PCTs) for the SBLOCA and LBLOCA analyses for MPS 2 and 3, NAPS 1 and 2, SPS 1 and 2 and VCS 1 are summarized below:

Millstone Unit 2 Millstone Unit 2 Small break - Framatome EM:

Large break - Framatome EM (Zr4 fuel):

1714°F 1845°F

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 2019 Annual 1 0 CFR 50.46 Report Page 2 of 4 Millstone Unit 2 Millstone Unit 3 Millstone Unit 3 North Anna Units 1 and 2 North Anna Units 1 and 2 Surry Units 1 and 2 Surry Units 1 and 2 Virgil C. Summer Unit 1 Virgil C. Summer Unit 1 Large break - Framatome EM (MS' fuel):

Small break - Westinghouse EM:

Large break - Westinghouse EM:

Small break - Westinghouse EM:

Large break - Westinghouse EM:

Small break - Westinghouse EM:

Large break - Westinghouse EM:

Small break - Westinghouse EM:

Large break - Westinghouse EM:

Slowdown:

Reflood 1:

Reflood 2:

Composite:

1615°F 1193°F 1933°F 1834.1°F 1982°F 2012°F 2071°F 1923°F 1814 °F 1814°F 1961 °F 1961 °F The LOCA results for MPS 2 and 3, NAPS 1 and 2, SPS 1 and 2 and VCS 1 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.

The information contained herein satisfies the 2019 annual reporting requirements of 10 CFR 50.46(a)(3)(ii).

If you have any questions regarding this submittal, please contact Mr. Gary D. Miller at (804) 273-2771.

Respectfully, Mark D. Sartain Vice President - Nuclear Engineering and Fleet Support Dominion Energy Nuclear Connecticut, Inc.

Dominion Energy South Carolina, Inc.

Virginia Electric and Power Company Commitments made in this letter: None

Attachments:

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 2019 Annual 10 CFR 50.46 Report Page 3 of 4

1. Report of Changes in Framatome and Westinghouse ECCS Evaluation Models

2. 2019 Annual Reporting of 10 CFR 50.46 Margin Utilization - Millstone Power Station Units 2 and 3

3. 2019 Annual Reporting of 10 CFR 50.46 Margin Utilization - North Anna Power Station Units 1 and 2

4. 2019 Annual Reporting of 10 CFR 50.46 Margin Utilization - Surry Power Station Units 1 and 2

5. 2019 Annual Reporting of 10 CFR 50.46 Margin Utilization - Virgil C. Summer Nuclear Station Unit 1 cc:

U. S. Nuclear Regulatory Commission, Region I Regional Administrator 2100 Renaissance Blvd., Suite 100 King of Prussia, PA 19406-2713 U. S. Nuclear Regulatory Commission, Region II Regional Administrator Marquis One Tower 245 Peachtree Center Ave., NE Suite 1200 Atlanta, Georgia 30303-1257 NRC Senior Resident Inspector Millstone Power Station NRC Senior Resident Inspector North Anna Power Station NRC Senior Resident Inspector Surry Power Station NRC Senior Resident Inspector Virgil C. Summer Power Station

Mr. G. Edward Miller NRC Project Manager - North Anna U.S. Nuclear Regulatory Commission One White Flint North Mail Stop 09 E3 11555 Rockville Pike Rockville, MD 20852-2738 Mr. R. Guzman Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 2019 Annual 10 CFR 50.46 Report Page 4 of 4 NRC Project Manager - Millstone Units 2 and 3 U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 C2 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Vaughn Thomas NRC Project Manager - Surry U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 04 F12 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Shawn Williams NRC Project Manager - Virgil C. Summer U. S. Nuclear Regulatory Commission One White Flint North Mail Stop 08 81A 11555 Rockville Pike Rockville, MD 20852-2738 Mr. Marcus Harris Old Dominion Electric Cooperative Innsbrook Corporate Center, Suite 300 4201 Dominion Blvd.

Glen Allen, Virginia 23060

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 2019 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 REPORT OF CHANGES IN FRAMATOME AND WESTINGHOUSE ECCS EVALUATION MODELS DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

VIRGINIA ELECTRIC AND POWER COMPANY DOMINION ENERGY SOUTH CAROLINA, INC.

MILLSTONE POWER STATION UNITS 2 AND 3 NORTH ANNA POWER STATION UNITS 1 AND 2 SURRY POWER STATION UNITS 1 AND 2 VIRGIL C. SUMMER NUCLEAR STATION UNIT 1

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 REPORT OF CHANGES IN FRAMATOME AND WESTINGHOUSE ECCS EVALUATION MODELS Millstone Power Station Unit 2

1.

Framatome identified no changes or errors applicable to the EMF-2328(P)(A)

Revision O with Supplement 1 evaluation model for Small Break LOCA (SBLOCA) for Millstone Unit 2 during 2019.

2.

Framatome identified no changes or errors applicable to the SEM/PWR-98 evaluation model for Large Break LOCA (LBLOCA) for Millstone Unit 2 during 2019.

This evaluation model is applicable to the Millstone Unit 2 fuel with Zr-4 cladding.

3.

On January 24, 2017, a new LBLOCA analysis was approved by the NRC based upon EMF-2103(P)(A), Revision 3, "Realistic Large Break LOCA (RLBLOCA)

Methodology for Pressurized Water Reactors." The new analysis is applicable to the AREVA Standard CE14 HTP fuel product with the M5' fuel rod cladding only. The analysis predicted a PCT of 1615°F.

Framatome identified the following changes and errors applicable to the EMF-2103(P)(A), Revision 3 evaluation model for RLBLOCA for Millstone Unit 2 during 2019.

Rod Pressure not Reset after Rupture in S-RELAP5 LOCA Calculations The error stems from S-RELAP5 failing to reset the COPERNIC fuel rod code rod internal pressure to the system pressure after S-RELAP5 determines the rod ruptures. Review of the COPERNIC model showed the heat transfer across the gap between the pellet and cladding was the main phenomenon affected by the internal rod pressure. Examination of the equations that COPERNIC solves to determine the gap heat conductance found the gas conductance and the gap size are affected by the reset in internal rod pressure. The equations clearly showed the internal pressure-related gas conductance and gap size effects are competing.

Due to the competing effects, the benchmarking data provided in BAW-10231 (P)(A)

Rev. 1 was evaluated to estimate the magnitude of the PCT impact. The evaluation resulted in a flPCT of 0°F for the Millstone Unit 2 RLBLOCA analysis.

A comprehensive evaluation of previous errors reported ensured no changes to the currently reported flPCTs.

Use of Oxide in S-RELAP5 Cathcart-Pawel Equation for Zirconium Metal Reacted An issue with the implementation of the Cathcart-Pawel correlation was identified.

The correlation is used for the calculation of metal-water reaction in the Framatome Page 1 of 7

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 EMF-2103(P)(A) Realistic Large Break LOCA (RLBLOCA) methodologies.

Cathcart-Pawel provided a set of equations for the rate constants associated with the oxidation process. In the RLBLOCA methodology, the correlation for the rate of oxide thickness was used instead of the correlation for the rate of total oxygen consumed.

The expected correlation based on the follow-on calculations in S-RELAP5 and the 10 CFR 50.46(b )(2) criterion is the total oxygen correlation.

Analyses performed with any version of the RLBLOCA methodology could be impacted.

As compared to a total oxygen-based implementation, the use of the oxide-based implementation led to a more conservative prediction of the transient oxidation and heat released during the reaction. The additional heat from the reaction could have resulted in higher calculated values of the analysis of record (AOR) peak clad temperature (PCT). However, for LBLOCA the degree of differences between the two correlation implementations has a negligible impact on PCT.

Millstone Power Station Unit 3

1.

Westinghouse did not identify any changes or errors applicable to the 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP for Millstone Unit 3 during 2019.

2.

Westinghouse identified the following changes and errors applicable to the 2004 Westinghouse Best Estimate (BE) LBLOCA Evaluation Model (EM) using the Automated Statistical Treatment of Uncertainty Method (ASTRUM) for Millstone Unit 3 during 2019:

General Code Maintenance Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451. The nature of these changes leads to an estimated peak cladding temperature impact of 0°F.

Core Barrel Heat Slab Error The Large Break Loss-of-Coolant Accident (LOCA) analysis of record for Millstone Unit 3 is documented in WCAP-16722-P, which utilizes the ASTRUM EM.

A calculation error was made in the core barrel metal heat slab, resulting in the volume of some of the core barrel heat slabs being overestimated. This represents an error in the application of the model for Millstone Unit 3, and a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451. The error is conservative, since Page 2 of 7

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 extra metal heat would promote downcomer boiling during reflood. A conservative 0°F is assigned for 10 CFR 50.46 reporting purposes.

Cold Leg Volume Error The LBLOCA analysis of record for Millstone Unit 3 utilizes the ASTRUM EM. An error was made in the calculation of the broken loop cold leg volume resulting in an under-prediction of the total reactor coolant system volume of less than 0.05%. This represents an error in the application of the evaluation model for Millstone Unit 3, and the correction of this error represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451. The difference in the broken loop cold leg volume is small and has been evaluated to have a negligible effect on the LBLOCA analysis results, leading to an estimated Peak Cladding Temperature (PCT) impact of 0°F.

Core Barrel Wetted Perimeter Error A calculation error was discovered in a wetted perimeter input in the vessel component of the Best Estimate Large Break Loss-of-Coolant Accident (BE LBLOCA) analysis-of-record. An evaluation of the impact was performed on the current licensing-basis analysis results. The error in the application of the model represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451. The difference in the wetted perimeter due to the error is very small and would be expected to produce a negligible effect on the LBLOCA analysis results, leading to an estimated PCT impact of 0°F for 10 CFR 50.46 reporting purposes.

Removal of the Vessel lnterfacial Heat Transfer Limit The Westinghouse Code Qualification Document (CQD) BE LBLOCA EM is documented in WCAP-12945-P-A. A limit on the vessel interfacial heat transfer was implemented into the WCOBRA/TRAC code as presented in Equation 5-12 therein.

The implementation of the limit was intended to prevent any extreme conditions which are detrimental to the robustness of the numerical method.

During the licensing of the method, the application of the limit was found to have a small impact on predicted results as discussed in the response to RAl1-116 of WCAP-12945-P-A.

An error was found in the implementation of the vessel interfacial heat transfer limit which effectively negates the application of the limit. The error was corrected by removing the vessel interfacial heat transfer limit from the WCOBRA/TRAC code (as opposed to a direct correction of the error).

Since the WCOBRA/TRAC code validation and sensitivity studies associated with the model from WCAP-12945-P-A all contained the error, the removal of the limit preserves the existing validation basis and sensitivity study conclusions that were presented in the topical report. Based Page 3 of 7

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 on the validation and RAI responses therein, it was concluded the as-coded interfacial heat transfer models and condensation behavior was acceptable.

The removal of the vessel interfacial heat transfer limit represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The removal of the vessel interfacial heat transfer limit was found to have negligible impact on the WCOBRA/TRAC code validation results. The validation results in combination with pressurized water reactor large break LOCA transient calculations and engineering judgement support an estimated peak cladding temperature impact of 0°F.

North Anna Power Station Units 1 and 2

1.

Westinghouse did not identify any changes or errors applicable to the 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP for North Anna Units 1 and 2 during 2019.

2.

Westinghouse identified the following changes and errors applicable to the 2004 Westinghouse BE LBLOCA EM using ASTRUM for North Anna Units 1 and 2 during 2019:

General Code Maintenance Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451. The nature of these changes leads to an estimated peak cladding temperature impact of 0°F.

Removal of the Vessel lnterfacial Heat Transfer Limit The Westinghouse Code Qualification Document (CQD) BE LBLOCA EM is documented in WCAP-12945-P-A. A limit on the vessel interfacial heat transfer was implemented into the WCOBRA/TRAC code as presented in Equation 5-12 therein.

The implementation of the limit was intended to prevent any extreme conditions which are detrimental to the robustness of the numerical method.

During the licensing of the method, the application of the limit was found to have a small impact on predicted results as discussed in the response to RAl1-116 of WCAP-12945-P-A.

An error was found in the implementation of the vessel interfacial heat transfer limit which effectively negates the application of the limit. The error was corrected by removing the vessel interfacial heat transfer limit from the WCOBRA/TRAC code (as opposed to a direct correction of the error).

Since the WCOBRA/TRAC code Page 4 of 7

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 validation and sensitivity studies associated with the model from WCAP-12945-P-A all contained the error, the removal of the limit preserves the existing validation basis and sensitivity study conclusions that were presented in the topical report. Based on the validation and RAI responses therein, it was concluded that the as-coded interfacial heat transfer models and condensation behavior was acceptable.

The removal of the vessel interfacial heat transfer limit represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The removal of the vessel interfacial heat transfer limit was found to have negligible impact on the WCOBRA/TRAC code validation results. The validation results in combination with pressurized water reactor large break LOCA transient calculations and engineering judgement support an estimated peak cladding temperature impact of 0°F.

Surry Power Station Units 1 and 2

1.

Westinghouse did not identify any changes or errors applicable to the 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP for Surry Units 1 and 2 during 2019.

2.

Westinghouse identified the following changes or errors applicable to the 2004 Westinghouse BE LBLOCA EM using ASTRUM for Surry Units 1 and 2 during 2019.

General Code Maintenance Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451. The nature of these changes leads to an estimated peak cladding temperature impact of 0°F.

Removal of the Vessel lnterfacial Heat Transfer Limit The Westinghouse Code Qualification Document (CQD) BE LBLOCA EM is documented in WCAP-12945-P-A. A limit on the vessel interfacial heat transfer was implemented into the WCOBRA/TRAC code as presented in Equation 5-12 therein.

The implementation of the limit was intended to prevent any extreme conditions which are detrimental to the robustness of the numerical method. During the licensing of the method, the application of the limit was found to have a small impact on predicted results as discussed in the response to RAI 1-116 of WCAP-12945-P-A.

Page 5 of 7

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 An error was found in the implementation of the vessel interfacial heat transfer limit which effectively negates the application of the limit. The error was corrected by removing the vessel interfacial heat transfer limit from the WCOBRA/TRAC code (as opposed to a direct correction of the error).

Since the WCOBRA/TRAC code validation and sensitivity studies associated with the model from WCAP-12945-P-A all contained the error, the removal of the limit preserves the existing validation basis and sensitivity study conclusions that were presented in the topical report. Based on the validation and RAI responses therein, it was concluded that the as-coded interfacial heat transfer models and condensation behavior was acceptable.

The removal of the vessel interfacial heat transfer limit represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The removal of the vessel interfacial heat transfer limit was found to have negligible impact on the WCOBRA/TRAC code validation results. The validation results in combination with pressurized water reactor large break LOCA transient calculations and engineering judgement support an estimated peak cladding temperature impact of 0°F.

Virgil C Summer

1.

Westinghouse did not identify any changes or errors applicable to the 1985 Westinghouse SBLOCA Evaluation Model with NOTRUMP for Virgil C. Summer during 2019.

2.

Westinghouse identified the following changes or errors applicable to the 2004 Westinghouse BE LBLOCA EM using ASTRUM for Virgil C. Summer during 2019.

General Code Maintenance Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include improving the input diagnostic checks; enhancing the code output; optimizing active coding; and eliminating inactive coding. These changes represent Discretionary Changes that will be implemented on a forward-fit basis in accordance with Section 4.1.1 of WCAP-13451. The nature of these changes leads to an estimated peak cladding temperature impact of 0°F.

Removal of the Vessel lnterfacial Heat Transfer Limit The Westinghouse Code Qualification Document (CQD) BE LBLOCA EM is documented in WCAP-12945-P-A. A limit on the vessel interfacial heat transfer was implemented into the WCOBRA/TRAC code as presented in Equation 5-12 therein.

The implementation of the limit was intended to prevent any extreme conditions which are detrimental to the robustness of the numerical method.

During the licensing of the method, the application of the limit was found to have a small impact Page 6 of 7

Serial No.20-219 Docket Nos. 50-336/423/338/339/280/281 /395 on predicted results as discussed in the response to RAI 1-116 of WCAP-12945-P-A.

An error was found in the implementation of the vessel interfacial heat transfer limit which effectively negates the application of the limit. The error was corrected by removing the vessel interfacial heat transfer limit from the WCOBRA/TRAC code (as opposed to a direct correction of the error).

Since the WCOBRA/TRAC code validation and sensitivity studies associated with the model from WCAP-12945-P-A all contained the error, the removal of the limit preserves the existing validation basis and sensitivity study conclusions that were presented in the topical report. Based on the validation and RAI responses therein, it was concluded that the as-coded interfacial heat transfer models and condensation behavior was acceptable.

The removal of the vessel interfacial heat transfer limit represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

The removal of the vessel interfacial heat transfer limit was found to have negligible impact on the WCOBRA/TRAC code validation results. The validation results in combination with pressurized water reactor large break LOCA transient calculations and engineering judgement support an estimated peak cladding temperature impact of 0°F.

Conclusion The LOCA results for Millstone Units 2 and 3, North Anna Units 1 and 2, Surry Units 1 and 2 and Virgil C. Summer Unit 1 are confirmed in the PCT rack-up tables, Attachments 2 through 5, to have 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) for calendar year 2019.

Page 7 of 7 Serial No.20-219 Docket Nos. 50-336/423 2019 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2019 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY NUCLEAR CONNECTICUT, INC.

MILLSTONE POWER STATION UNITS 2 AND 3

10 CFR 50.46 MARGIN UTILIZATION - SMALL BREAK LOCA Plant Name:

Millstone Power Station, Unit 2 Serial No.20-219 Docket Nos. 50-336/423 Utility Name:

Dominion Energy Nuclear Connecticut, Inc.

Analysis Information EM:

2015, Supp. 1, SBLOCA, S-RELAP5 Based Limiting Break Size: 3.78 Inches Analysis Date:

April 2015 Vendor:

Frarnatorne Peak Linear Power: 15.1 kW/ft Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Zirc-4 Product Penalty

2.

M5 LOCA Swelling and Rupture

3.

S-RELAP5 Oxidation Calculations B.

Planned Plant Modification Evaluations

1.

None C.

2019 ECCS Model Assessments

1.

None D.

Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS Page 1 of 7 PCT=

Clad Temp{°F) 1707 4

0 3

0 0

0 1714

Serial No.20-219 Docket Nos. 50-336/423 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name:

Millstone Power Station, Unit 2 (Zr4 Fuel)

Dominion Energy Nuclear Connecticut, Inc.

Utility Name:

Analysis Information EM:

SEM/PWR-98 Limiting Break Size: 1.0 DECLG Analysis Date:

November 1998 Vendor:

Framatome Peak Linear Power: 15.1 kW/ft Notes:

None Clad Temp{°F)

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 ofReflood

-2

4.

SISPUNCH/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.

RFP AC 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

25.

Array Index Issues in the RELAP4 Code 0

26.

Millstone Unit 3 Cycle 20 PBOT/PMID Violations 0

B.

Planned Plant Modification Evaluations

1.

None 0

C.

2019 ECCS Model Assessments

1. None 0

Page 2 of 7

D.

Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS Page 3 of 7 Serial No.20-219 Docket Nos. 50-336/423 0

PCT=

1845

Serial No.20-219 Docket Nos. 50-336/423 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name:

Utility Name:

Millstone Power Station, Unit 2 (M5 Fuel)

Dominion Energy Nuclear Connecticut, Inc.

Analysis Information EM:

EMF-2103 Limiting Break Size: 1.0 DEGB Analysis Date:

May 2016*

Vendor:

Frarnatome Peak Linear Power: 15.1 kW/ft Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Placement of Hot Leg Piping Form Loss Coefficient B.

C.

D.

2.

M5 LOCA Swelling and Rupture

3.

S-RELAP5 Oxidation Calculations Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessment

1.

Cathcart-Pawel correlation implementation

2.

Rod pressure not reset after rupture in S-RELAP5 LOCA calculations Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

Clad Temp{°F) 1615 0

0 0

1615

Note that the date of the Analysis of Record differs from that reported previously. This is a change to the date of completion of the analysis rather than the date of approval by the NRC.

Page 4 of 7

10 CFR 50.46 MARGIN UTILIZATION - SMALL BREAK LOCA Plant Name:

Millstone Power Station, Unit 3 Utility Name:

Dominion Energy Nuclear Connecticut, Inc.

Analysis Information EM:

NOTRUMP Limiting Break Size:

Analysis Date:

02/07 /07 Vendor:

Westinghouse FQ:

2.6 Fuel:

RFA-2 Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments FdH:

SGTP (%):

1.65 10

1.

Errors in Reactor Vessel Lower Plenum Surface Area Calculations

2.

Discrepancy in Metal Masses Used from Drawings Serial No.20-219 Docket Nos. 50-336/423 4 inches Clad Temp (°F) 1193

3.

Urania-Gadolinia Pellet Thermal Conductivity Calculation 0

0 0

0

4.

Pellet Crack and Dish Volume Calculation

5.

Treatment of Vessel Average Temperature Uncertainty

6.

Maximum Fuel Rod Time Step Logic

7.

Radiation Heat Transfer Logic

8.

NOTRUMP-EM Evaluation of Fuel Pellet Thermal

9.

10.

11.

12.

13.

14.

15.

16.

Conductivity Degradation SBLOCTA Cladding Strain Requirement for Fuel Rod Burst Fuel Rod Gap Conductance Error Radiation Heat Transfer Model Error SBLOCTA Pre-DNB Cladding Heat Transfer Coefficient Calculation Insertion of AXIOM' Cladding LTAs Vessel Average Temperature Uncertainty Error in the Upper Plenum Fluid Volume Calculation UO2 Fuel Pellet Heat Capacity B.

Planned Plant Modification Evaluations

1.

None C.

2019 ECCS Model Assessments

1.

None D.

Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

Page 5 of 7 0

0 0

0 1193

Serial No.20-219 Docket Nos. 50-336/423 10 CFR 50.46 MARGIN UTILIZATION - LARGE BREAK LOCA Plant Name:

Millstone Power Station, Unit 3 Utility Name:

Dominion Energy Nuclear Connecticut, Inc.

Analysis Information EM:

ASTRUM (2004)

Limiting Break Size:

Analysis Date:

04/17 /07 Vendor:

Westinghouse FQ:

2.6 FdH:

Fuel:

RFA-2 SGTP (%):

Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

HOTSPOT Burst Temperature Logic Errors

2.

CCFL Global Volume Error

3.

HOTSPOT Gap Heat Transfer Logic

4.

Discrepancy in Metal Masses Used from Drawings 1.65 10

5.

Error in ASTRUM Processing of Average Rod Burnup and Rod Internal Pressure

6.

Treatment of Vessel Average Temperature Uncertainty

7.

PBOT and PMID Evaluation

8.

Evaluation of Fuel Pellet Thermal Conductivity Degradation

9.

HOTSPOT Burst Temperature Calculation for ZIRLO Cladding

10.

Rod Internal Pressure Calculation

11.

HOTSPOT Iteration Algorithm for Calculating the Initial Fuel Pellet Average Temperature

12.

WCOBRA/TRAC Thermal-Hydraulic History File Dimension used in HSDRIVER Background

13.

WCOBRA/TRAC Automated Restart Process Logic Error

14.

Initial Fuel Pellet Average Temperature Uncertainty Calculation

15.

16.

17.

18.

19.

20.

21.

22.

23.

24.

25.

Elevations for Heat Slab Temperature Initialization Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Heat Transfer Logic Correction for Rod Burst Calculation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Corrections Correction to the Pipe Exit Pressure Drop Error WCOBRA/TRAC Ul 9 File Dimension Error Correction Page 6 of 7 Guillotine Clad Temp (°F) 1781 0

0 0

222 0

0 0

26.

27.

28.

29.

30.

31.

32.

33.

34.

35.

36.

37.

38.

39.

40.

41.

Serial No.20-219 Docket Nos. 50-336/423 Revised Heat Transfer Multiplier Distributions HOTSPOT Burst Strain Error Correction Changes to Grid Blockage Ratio and Porosity Grid Heat Transfer Enhancement Calculation Burst Elevation Selection Errors in Decay Group Uncertainty Factors Errors in Support Plate, Core Barrel, and Vessel Wall Unheated Conductor Error in Oxidation Calculations Error in use of ASME Steam Tables Insertion of AXIOM' Cladding LTAs Vessel Average Temperature Uncertainty Inconsistent Application of Numerical Ramp Applied to the Entrained Liquid / Vapor Interfacial Drag Coefficient Inappropriate Resetting of Transverse Liquid Mass Flow Steady-State Fuel Temperature Calibration Method Millstone Unit 3 Cycle 20 PBOT/PMID Violations Vapor Temperature Resetting

-91 21 0

0 0

0 B.

Planned Plant Modification Evaluations

1.

None C.

2019 ECCS Model Assessments

1.

Core Barrel Heat Slab Error

2.

Cold Leg Volume Error

3.

Core Barrel Wetted Perimeter Error

4.

Removal of the Vessel Interfacial Heat Transfer Limit D.

Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS Page 7 of 7 PCT=

0 0

0 1933

ATTACHMENT 3 Serial No.20-219 Docket Nos. 50-338/339 2019 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM {ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2019 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

NORTH ANNA POWER STATION UNITS 1 AND 2

Serial No.20-219 Docket Nos. 50-338/339 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name:

Utility Name:

North Anna Power Station, Unit 1 Virginia Electric and Power Company Analysis Information EM:

NOTRUMP Limiting Break Size:

Analysis Date:

12/20/2010 Vendor:

Westinghouse FQ:

2.32 FAH:

1.65 Fuel:

RFA-2 SGTP (%):

7 Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

NOTRUMP-EM Evaluation of Fuel Pellet Thermal B.

C.

D.

2.

3.

4.

5.

6.

7.

Conductivity Degradation SBLOCA Cladding Strain Requirement for Fuel Rod Burst Fuel Rod Gap Conductance Error Radiation Heat Transfer Model Error SBLOCT A Pre-DNB Cladding Heat Transfer Coefficient Calculation Error in the Upper Plenum Fluid Volume Calculation UO2 Fuel Pellet Heat Capacity Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

None Other

1.

None 2.75 inches Clad Temp (°F) 1834.1 0

0 0

0 LICENSING BASIS PCT + PCT ASSESSMENTS PCT= 1834.1 Page 1 of 6

Serial No.20-219 Docket Nos. 50-338/339 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name:

Utility Name:

North Anna Power Station, Unit 1 Virginia Electric and Power Company Analysis Information EM:

ASTRUM (2004)

Limiting Break Size:

Analysis Date:

8/25/2010 Vendor:

Westinghouse FQ:

2.32 FAR:

1.65 Fuel:

RFA-2 SGTP (%):

7 DEGB Notes: Core Power :5:100% of2951 MWt; SG Model 54F; 17xl7 RFA-2 Fuel with ZIRLO or OptimizedZIRLO' cladding, Non-IFBA or IFBA, IFMs Clad Temp (°F)

LICENSING BASIS Analysis of Record PCT 1852 PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Evaluation of Fuel Pellet Thermal Conductivity 135 Degradation

2.

HOTSPOT Burst Temperature Calculation 0

for ZIRLO Cladding

3.

Rod Internal Pressure Calculation 0

4.

HOTSPOT Iteration Algorithm for Calculating the 0

Initial Fuel Pellet Average Temperature

5.

WCOBRA/TRAC Thermal-Hydraulic History File 0

Dimension used in HSDRIVER Background

6.

WCOBRA/TRAC Automated Restart Process Logic Error 0

7.

Initial Fuel Pellet Average Temperature Uncertainty 1

Calculation

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

23.

Elevations for Heat Slab Temperature Initialization Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Heat Transfer Logic Correction for Rod Burst Calculation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Corrections Correction to the Pipe Exit Pressure Drop Error WCOBRA/TRAC U19 File Dimension Error Correction Revised Heat Transfer Multiplier Distributions HOTSPOT Burst Strain Error Correction Changes to Grid Blockage Ratio and Porosity Grid Heat Transfer Enhancement Calculation Vessel Section 7 Mid-Level Elevation Modeling Page 2 of 6 0

0 0

-27 21 0

0 0

B.

C.

Serial No.20-219 Docket Nos. 50-338/339

24.

25.

26.

27.

28.

29.

30.

31.

32.

33.

Burst Elevation Selection Errors in Decay Group Uncertainty Factors Error in Oxidation Calculations Error in use of ASME Steam Tables Support Column Core Barrel Unheated Conductor Errors0 Inconsistent Application of Numerical Ramp Applied to the Entrained Liquid / Vapor Interfacial Drag Coefficient Inappropriate Resetting of Transverse Liquid Mass Flow Steady-State Fuel Temperature Calibration Method Correction to Fuel Pellet TCD Assessment Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit 0

0 0

0 D.

Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

1982 Page 3 of 6

Serial No.20-219 Docket Nos. 50-338/339 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name:

North Anna Power Station, Unit 2 Virginia Electric and Power Company Utility Name:

Analysis Information EM:

NOTRUMP Limiting Break Size:

Analysis Date:

12/20/2010 Vendor:

Westinghouse FQ:

2.32 FAH:

1.65 Fuel:

RFA-2 SGTP (%):

7 Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

NOTRUMP-EM Evaluation of Fuel Pellet Thermal B.

C.

D.

2.

3.

4.

5.

6.

7.

Conductivity Degradation SBLOCTA Cladding Strain Requirement for Fuel Rod Burst Fuel Rod Gap Conductance Error Radiation Heat Transfer Model Error SBLOCTA Pre-DNB Cladding Heat Transfer Coefficient Calculation Error in the Upper Plenum Fluid Volume Calculation UO2 Fuel Pellet Heat Capacity Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

None Other

1.

None 2.75 inches Clad Temp {°F) 1834.1 0

0 0

0 LICENSING BASIS PCT+ PCT ASSESSMENTS PCT= 1834.1 Page 4 of 6

Serial No.20-219 Docket Nos. 50-338/339 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name:

Utility Name:

North Anna Power Station, Unit 2 Virginia Electric and Power Company Analysis Information EM:

ASTRUM (2004)

Limiting Break Size:

Analysis Date:

8/25/2010 Vendor:

Westinghouse FQ:

2.32 FMI:

1.65 Fuel:

RFA-2 SGTP (%):

7 DEGB Notes: Core Power s100% of2951 MWt; SG Model 54F; 17x17 RFA-2 Fuel with ZIRLO orOptimizedZIRLO' cladding, Non-IFBA or IFBA, IFMs Clad Temp (°F)

LICENSING BASIS Analysis of Record PCT 1852 PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Evaluation of Fuel Pellet Thermal Conductivity 135 Degradation

2.

HOTSPOT Burst Temperature Calculation 0

for ZIRLO Cladding

3.

Rod Internal Pressure Calculation 0

4.

HOTSPOT Iteration Algorithm for Calculating the 0

Initial Fuel Pellet Average Temperature

5.

WCOBRA/TRAC Thermal-Hydraulic History File 0

Dimension used in HSDRIVER Background

6.

WCOBRA/TRAC Automated Restart Process Logic Error 0

7.

Initial Fuel Pellet Average Temperature Uncertainty 1

Calculation

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

18.

19.

20.

21.

22.

Elevations for Heat Slab Temperature Initialization Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Heat Transfer Logic Correction for Rod Burst Calculation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Corrections Correction to the Pipe Exit Pressure Drop Error WCOBRA/TRAC U19 File Dimension Error Correction Revised Heat Transfer Multiplier Distributions HOTSPOT Burst Strain Error Correction Changes to Grid Blockage Ratio and Porosity Grid Heat Transfer Enhancement Calculation Page 5 of 6 0

0 0

-27 21 0

0

B.

C.

Serial No.20-219 Docket Nos. 50-338/339

23.

24.

25.

27.

28.

29.

30.

31.

32.

33.

34.

Vessel Section 7 Mid-Level Elevation Modeling Burst Elevation Selection Errors in Decay Group Uncertainty Factors Error in Oxidation Calculations Error in use of ASME Steam Tables Support Column Core Barrel Unheated Conductor Errors Inconsistent Application of Numerical Ramp Applied to the Entrained Liquid / Vapor Interfacial Drag Coefficient Inappropriate Resetting of Transverse Liquid Mass Flow Steady-State Fuel Temperature Calibration Method Correction to Fuel Pellet TCD Assessment Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit 0

0 0

D.

Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

1982 Page 6 of 6

ATTACHMENT 4 Serial Number 20-219 Docket Nos. 50-280/281 2019 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2019 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)

SURRY POWER STATION UNITS 1 AND 2

Serial No.20-219 Docket Nos. 50-280/281 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE SMALL BREAK LOCA Plant Name:

Surry Power Station, Unit 1 Utility Name:

Virginia Electric and Power Company Analysis Information EM:

NOTRUMP Limiting Break Size:

2.75 inches Analysis Date:

5/7/2009 Vendor:

Westinghouse FQ:

2.5 FMI:

1.7 Fuel:

Upgrade SGTP (%):

7 Notes:

None Clad Temp {°F)

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

A.

Prior ECCS Model Assessments B.

C.

D.

1.

Urania-Gadolinia Pellet Thermal Conductivity Calculation.

0

2.

Pellet Crack and Dish Volume Calculation.

0

3.

Treatment of Vessel Average Temperature Uncertainty 0

4.

15Xl5 Upgrade Fuel 0

5.

Maximum Fuel Rod Time Step Logic 0

6.

Radiation Heat Transfer Logic 0

7.

NOTRUMP-EM Evaluation of Fuel Pellet Thermal 0

8.

9.

10.

11.

12.

13.

Conductivity Degradation SBLOCTA Cladding Strain Requirement for Fuel Rod Burst Fuel Rod Gap Conductance Error Radiation Heat Transfer Model Error SBLOCTA Pre-DNB Cladding Heat Transfer Coefficient Calculation Error in the Upper Plenum Fluid Volume Calculation UO2 Fuel Pellet Heat Capacity Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

None Other

1.

None 0

0 0

LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

2012 Page 1 of 6

Serial No.20-219 Docket Nos. 50-280/281 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA Plant Name:.

Utility Name:

Surry Power Station, Unit 1 Virginia Electric and Power Company Analysis Information EM:

ASTRUM (2004)

Limiting Break Size:

Analysis Date:

10/6/2010 Vendor:

Westinghouse FQ:

2.5 FAR:

1.7 Fuel:

Upgrade SGTP (%):

7 Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Evaluation of Fuel Pellet Thermal Conductivity Degradation

2.

Pellet Radial Profile Option

3.

HOTSPOT Burst Temperature Calculation for ZIRLO Cladding

4.

Rod Internal Pressure Calculation

5.

HOTSPOT Iteration Algorithm for Calculating the Initial Fuel Pellet Average Temperature

6.

WCOBRA/TRAC Thermal-Hydraulic History File Dimension used in HSDRIVER Background

7.

WCOBRA/TRAC Automated Restart Process Logic Error

8.

Initial Fuel Pellet Average Temperature Uncertainty Calculation

9.

Elevations for Heat Slab Temperature Initialization

10.

Heat Transfer Model Error Corrections

11.

Correction to Heat Transfer Node Initialization

12.

Mass Conservation Error Fix

13.

Correction to Split Channel Momentum Equation

14.

Heat Transfer Logic Correction for Rod Burst Calculation

15.

Changes to Vessel Superheated Steam Properties

16.

Update to Metal Density Reference Temperatures

17.

Decay Heat Model Error Corrections

18.

Correction to the Pipe Exit Pressure Drop Error

19.

WCOBRA/TRAC U19 File Dimension Error Correction

20.

Revised Heat Transfer Multiplier Distributions

21.

HOTSPOT Burst Strain Error Correction

22.

Changes to Grid Blockage Ratio and Porosity

23.

Grid Heat Transfer Enhancement Calculation

24.

Vessel Section 7 Mid-Level Elevation Modeling Page 2 of 6 DEG Clad Temp {°F) 1853 183

-13 0

0 0

-7 51 0

0 0

B.

C.

D.

25.

26.

27.

28.

29.

30.

31.

32.

Burst Elevation Selection Errors in Decay Group Uncertainty Factors Evaluation of Additional Containment Metal Error in Oxidation Calculations Error in use of ASME Steam Tables Core Barrel Unheated Conductor Errors Discrepancy in Wetted Perimeter Inputs Inconsistent Application of Numerical Ramp Applied Serial No.20-219 Docket Nos. 50-280/281 0

4 0

0 0

0

33.

34.

35.

to the Entrained Liquid / Vapor Interfacial Drag Coefficient Inappropriate Resetting of Transverse Liquid Mass Flow Steady-State Fuel Temperature Calibration Method 0

0 0

Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 0

2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit 0

Other

1.

None 0

LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

2071 Page 3 of 6

Serial No.20-219 Docket Nos. 50-280/281 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:

Analysis Date:

5/7/2009 Vendor:

Westinghouse FQ:

2.5 FAR:

1.7 Fuel:

Upgrade SGTP (%):

7 Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments B.

C.

D.

I.

Urania-Gadolinia Pellet Thermal Conductivity Calculation.

2.

Pellet Crack and Dish Volume Calculation.

3.

Treatment of Vessel Average Temperature Uncertainty

4.

15X15 Upgrade Fuel

5.

Maximum Fuel Rod Time Step Logic

6.

Radiation Heat Transfer Logic

7.

NOTRUMP-EM Evaluation of Fuel Pellet Thermal

8.

9.

10.

11.

12.

13.

Conductivity Degradation SBLOCT A Cladding Strain Requirement for Fuel Rod Burst Fuel Rod Gap Conductance Error Radiation Heat Transfer Model Error SBLOCTA Pre-DNB Cladding Heat Transfer Coefficient Calculation Error in the Upper Plenum Fluid Volume Calculation UO2 Fuel Pellet Heat Capacity Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

None Other

1.

None LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

Page 4 of 6 2.75 inches Clad Temp {°F) 2012 0

0 0

0 2012

Serial No.20-219 Docket Nos. 50-280/281 10 CFR 50.46 MARGIN UTILIZATION - WESTINGHOUSE LARGE BREAK LOCA 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:

10/6/2010 Vendor:

Westinghouse FQ:

2.5 FMI:

1.7 Fuel:

Upgrade SGTP (%):

7 Notes:

None Clad Temp (°F)

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

A.

Prior ECCS Model Assessments

1.

Evaluation of Fuel Pellet Thermal Conductivity 183 Degradation

2.

Pellet Radial Profile Option

-13

3.

HOTSPOT Burst Temperature Calculation 0

for ZIRLO Cladding

4.

Rod Internal Pressure Calculation 0

5.

HOTSPOT Iteration Algorithm for Calculating the 0

Initial Fuel Pellet Average Temperature

6.

WCOBRA/TRAC Thermal-Hydraulic History File 0

Dimension used in HSDRIVER Background

7.

WCOBRA/TRAC Automated Restart Process Logic Error 0

8.

Initial Fuel Pellet Average Temperature Uncertainty 0

Calculation

9.

Elevations for Heat Slab Temperature Initialization 0

10.

Heat Transfer Model Error Corrections 0

11.

Correction to Heat Transfer Node Initialization 0

12.

Mass Conservation Error Fix 0

13.

Correction to Split Channel Momentum Equation 0

14.

Heat Transfer Logic Correction for Rod Burst Calculation 0

15.

Changes to Vessel Superheated Stearn Properties 0

16.

Update to Metal Density Reference Temperatures 0

17.

Decay Heat Model Error Corrections 0

18.

Correction to the Pipe Exit Pressure Drop Error 0

19.

WCOBRA/TRAC U19 File Dimension Error Correction 0

20.

Revised Heat Transfer Multiplier Distributions

-7

21.

HOTSPOT Burst Strain Error Correction 51

22.

Changes to Grid Blockage Ratio and Porosity 0

23.

Grid Heat Transfer Enhancement Calculation 0

24.

Vessel Section 7 Mid-Level Elevation Modeling 0

25.

Burst Elevation Selection 0

Page 5 of 6

B.

C.

D.

26.

27.

28.

29.

30.

31.

32.

Errors in Decay Group Uncertainty Factors Evaluation of Additional Containment Metal Error in Oxidation Calculations Error in use of ASME Steam Tables Core Barrel Unheated Conductor Errors Discrepancy in Wetted Perimeter Inputs Inconsistent Application of Numerical Ramp Applied Serial No.20-219 Docket Nos. 50-280/281 4

0 0

33.

34.

35.

to the Entrained Liquid / Vapor Interfacial Drag Coefficient Inappropriate Resetting of Transverse Liquid Mass Flow0 Steady-State Fuel Temperature Calibration Method 0

0 Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 0

2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit 0

Other

1.

None 0

LICENSING BASIS PCT + PCT ASSESSMENTS PCT=

2071 Page 6 of 6

ATTACHMENT 5 Serial No.20-219 Docket No. 50-395 2019 ANNUAL REPORT OF EMERGENCY CORE COOLING SYSTEM (ECCS) MODEL CHANGES PURSUANT TO THE REQUIREMENTS OF 10 CFR 50.46 2019 ANNUAL REPORTING OF 10 CFR 50.46 MARGIN UTILIZATION DOMINION ENERGY SOUTH CAROLINA, INC.

VIRGIL C. SUMMER NUCLEAR STATION UNIT 1

10 CFR 50.46 MARGIN UTILIZATION -APPENDIX K SMALL BREAK Plant Name:

V. C. Summer Utility Name:

Dominion Energy South Carolina Analysis Information EM:

NOTRUMP Analysis Date:

Limiting Break Size:

February 2003 Westinghouse 1.62 3 Inch Vendor:

FQ:

2.45 FdH:

Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

2.

3.

4

5.

6.

7.

8.

9.

10.

11.

12.

13.

14.

15.

16.

17.

NOTRUMP-EM Refined Break Spectrum Errors in Reactor Vessel Nozzle Data Collections Pump Weir Resistance Modeling Errors in Reactor Vessel Lower Plenum Surface Area Calculations Modeling of Annular Pellets Discrepancy in Metal Masses Used from Drawings V. C. Summer Upflow Conversion Treatment of Vessel Average Temperature Uncertainty Urania-Gadolinia Pellet Thermal Conductivity Calculation Pellet Crack and Dish Volume Calculation Radiation Heat Transfer Logic Maximum Fuel Rod Time Step Logic NOTRUMP-EM Evaluation of Fuel Pellet Thermal Conductivity Degradation SBLOCTA Cladding Strain Requirement for Fuel Rod Burst Fuel Rod Gap Conductance Error Radiation Heat Transfer Model Error SBLOCTA Pre-DNB Cladding Surface Heat Transfer Coefficient Calculation

18.

19.

20.

21.

Control Rod Drop Time Technical Specification Change Vessel Average Temperature Uncertainty B.

C.

D.

Error in the Upper Plenum Fluid Volume Calculation UO2 Fuel Pellet Heat Capacity Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

None Other

1.

None LICENSING BASIS PCT+ PCT ASSESSMENTS Page 1 of 9 PCT=

Serial No.20-219 Docket No. 50-395 Clad Temp(0F) 1775 0

0 0

0 148 0

0 0

1923

Serial No.20-219 Docket No. 50-395 10 CFR 50.46 MARGIN UTILIZATION - BEST ESTIMATE LARGE BREAK BLOWDOWN Plant Name:

V. C. Summer Utility Name:

Dominion Energy South Carolina Analysis Information EM:

CQD (1996)

Analysis Date:

Limiting Break Size:

February 2003 Westinghouse 1.7 DEGB Vendor:

FQ:

2.5 FdH:

Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Fan Cooler Performance Increase

2.

Improved Automation of End ofBlowdown Time

3.

Implementation of ASTRUM Capability in HOTSPOT 4

Revised Blowdown Heatup Uncertainty Distribution

5.

Revised Iteration Algorithm for Calculating The Average Fuel Temperature

6.

Improved Automation of End ofBlowdown Time

7.

Thermodynamic Properties from Thermo

8.

Pressurizer Fluid Volumes

9.

Vessel Unheated Conductor Noding

10.

Containment Relative Humidity Assumption

11.

HOTSPOT Fuel Relocation

12.

Steam Generator Nozzle Volume Accounting Error

13.

Cold Leg Volume Discrepancy

14.

Errors in Reactor Vessel Nozzle Data Collection

15.

HOTSPOT Burst Temperature Logic Errors

16.

V. C. Summer Upflow Conversion

17.

Zero Cross-Flow Boundary Condition Error

18.

Discrepancy in Metal Masses Used from Drawings

19.

HOTSPOT Gap Heat Transfer Logic

20.

HOTSPOT Statistical Output Logic

21.

Treatment of Vessel Average Temperature Uncertainty

22.

Additional Heat Sinks and Maximum Spray Flow

23.

Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown

24.

PAD 4.0 Implementation

25.

Zero Cross-Flow Boundary Condition Error

26.

HOTSPOT Burst Temperature Calculation For ZIRLO Cladding

27.

HOTSPOT Iteration Algorithm for Calculating The Initial Fuel Pellet Average Temperature

28.

WCOBRA/TRAC Automated Restart Process Logic Error

29.

Rod Internal Pressure Calculation

30.

WCOBRA/TRAC Thermal-Hydraulic History File Dimension used in HSDRIVER Page 2 of 9 Clad Temp(0 F) 1860 0

0 0

49 0

0 0

-7 0

0 0

-83 0

0 0

0

B.

C.

D.

31.

32.

33.

34.

35.

36.

37.

38.

39.

40.

41

42.

43.

44.

45.

46.

47.

48.

49.

50.

51.

52.

53.

54.

Burst Elevation Selection Elevation for Heat Slab Temperature Initialization Heat Transfer Logic for Rod Burst Calculation WCOBRA/TRAC U19 File Dimension Error Correction Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Correction Correction to the Pipe Exit Pressure Drop Error Vessel Section 7 Mid-Level Elevation Modeling Grid Heat Transfer Enhancement Calculation Revised Heat Transfer Multiplier Distributions Changes to Grid Blockage Ratio and Porosity Error in Burst Strain Application Code Uncertainty in BE LBLOCA Monte Carlo Simulations Error in Oxidation Calculations Support Column Unheated Conductor Error Vessel Average Temperature Uncertainty Numerical Ramp Entrained LiquidN apor Interfacial Drag Inappropriate Resetting of Transverse Liquid Mass Flow Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit Other

1.

None LICENSING BASIS PCT+ PCT ASSESSMENTS PCT=

Page 3 of 9 Serial No.20-219 Docket No. 50-395 0

0 0

0

-5 0

0 0

0 1814

Serial No.20-219 Docket No. 50-395 10 CFR 50.46 MARGIN UTILIZATION - BEST ESTIMATE LARGE BREAK REFLOOD 1 Plant Name:

V. C. Summer Utility Name:

Dominion Energy South Carolina Analysis Information EM:

CQD (1996)

Analysis Date:

Limiting Break Size:

Febmary 2003 Westinghouse 1.7 DEGB Vendor:

FQ:

2.5 FdH:

Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Fan Cooler Performance Increase

2.

Improved Automation of End ofBlowdown Time

3.

Implementation of ASTRUM Capability in HOTSPOT 4

Revised Blowdown Heatup Uncertainty Distribution

5.

Revised Iteration Algorithm for Calculating The Average Fuel Temperature

6.

Improved Automation of End ofBlowdown Time

7.

Thermodynamic Properties from Thermo

8.

Pressurizer Fluid Volumes

9.

Vessel Unheated Conductor Noding

10.

Containment Relative Humidity Assumption

11.

HOTSPOT Fuel Relocation

12.

Steam Generator Nozzle Volume Accounting Error

13.

Cold Leg Volume Discrepancy

14.

Errors in Reactor Vessel Nozzle Data Collection

15.

HOTSPOT Burst Temperature Logic Errors

16.

V. C. Summer Upflow Conversion

17.

Zero Cross-Flow Boundary Condition Error

18.

Discrepancy in Metal Masses Used from Drawings

19.

HOTSPOT Gap Heat Transfer Logic

20.

HOTSPOT Statistical Output Logic

21.

Treatment of Vessel Average Temperature Uncertainty

22.

Additional Heat Sinks and Maximum Spray Flow

23.

Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Burndown

24.

PAD 4.0 Implementation

25.

Zero Cross-Flow Boundary Condition Error

26.

HOTSPOT Burst Temperature Calculation For ZIRLO Cladding

27.

HOTSPOT Iteration Algorithm for Calculating The Initial Fuel Pellet Average Temperature

28.

WCOBRA/TRAC Automated Restart Process Logic Error

29.

Rod Internal Pressure Calculation

30.

WCOBRA/TRAC Thermal-Hydraulic History File Dimension used in HSDRIVER Page 4 of 9 Clad Temp(OF) 1808 1

0 0

5 0

0 0

-44 0

0 0

0 113

-118 0

0 0

0

B.

C.

D.

31.

32.

33.

34.

35.

36.

37.

38.

39.

40.

41.

42.

43.

44.

45.

46.

47.

48.

49.

50.

51.

52.

53.

54.

Burst Elevation Selection Elevation for Heat Slab Temperature Initialization Heat Transfer Logic for Rod Burst Calculation WCOBRA/TRAC U19 File Dimension Error Correction Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Correction Correction to the Pipe Exit Pressure Drop Error Vessel Section 7 Mid-Level Elevation Modeling Grid Heat Transfer Enhancement Calculation Revised Heat Transfer Multiplier Distributions Changes to Grid Blockage Ratio and Porosity Error in Burst Strain Application Code Uncertainty in BE LBLOCA Monte Carlo Simulations Error in Oxidation Calculations Support Column Unheated Conductor Error Vessel Average Temperature Uncertainty Numerical Ramp Entrained LiquidN apor Interfacial Drag Inappropriate Resetting of Transverse Liquid Mass Flow Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments I.

Removal of the Vessel Interfacial Heat Transfer Limit Other I.

None LICENSING BASIS PCT+ PCT ASSESSMENTS PCT=

Page 5 of 9 Serial No.20-219 Docket No. 50-395 0

0 0

0 5

24 20 0

0 0

0 1814

Serial No.20-219 Docket No. 50-395 10 CFR 50.46 MARGIN UTILIZATION - BEST ESTIMATE LARGE BREAK REFLOOD 2 Plant Name:

V. C. Summer Utility Name:

Dominion Energy South Carolina Analysis Information EM:

CQD (1996)

Analysis Date:

Limiting Break Size:

February 2003 Westinghouse 1.7 DEGB Vendor:

FQ:

2.5 FdH:

Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Fan Cooler Performance Increase

2.

Improved Automation of End ofBlowdown Time

3.

Implementation of ASTRUM Capability in HOTSPOT 4

Revised Blowdown Heatup Uncertainty Distribution

5.

Revised Iteration Algorithm for Calculating The Average Fuel Temperature

6.

Improved Automation of End ofBlowdown Time

7.

Thermodynamic Properties from Thermo

8.

Pressurizer Fluid Volumes

9.

Vessel Unheated ConductorNoding

10.

Containment Relative Humidity Assumption

11.

HOTSPOT Fuel Relocation

12.

Steam Generator Nozzle Volume Accounting Error

13.

Cold Leg Volume Discrepancy

14.

Errors in Reactor Vessel Nozzle Data Collection

15.

HOTSPOT Burst Temperature Logic Errors

16.

V. C. Summer Upflow Conversion

17.

Zero Cross-Flow Boundary Condition Error

18.

Discrepancy in Metal Masses Used from Drawings

19.

HOTSPOT Gap Heat Transfer Logic

20.

HOTSPOT Statistical Output Logic

21.

Treatment of Vessel Average Temperature Uncertainty

22.

Additional Heat Sinks and Maximum Spray Flow

23.

Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown

24.

PAD 4.0 Implementation

25.

Zero Cross-Flow Boundary Condition Error

26.

HOTSPOT Burst Temperature Calculation For ZIRLO Cladding

27.

HOTSPOT Iteration Algorithm for Calculating The Initial Fuel Pellet Average Temperature

28.

WCOBRA/TRAC Automated Restart Process Logic Error

29.

Rod Internal Pressure Calculation

30.

WCOBRA/TRAC Thermal-Hydraulic History File Dimension used in HSDRlVER Page 6 of 9 Clad Temp{°F) 1988 2

0 0

5 0

0 0

-29 0

0 0

1 123

-118 0

0 0

0

B.

C.

D.

31.

32.

33.

34.

35.

36.

37.

38.

39.

40.

41.

42.

43.

44.

45.

46.

47.

48.

49.

50.

51.

52.

53.

54.

Burst Elevation Selection Elevation for Heat Slab Temperature Initialization Heat Transfer Logic for Rod Burst Calculation WCOBRA/TRAC U19 File Dimension Error Correction Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Corrections Correction to the Pipe Exit Pressure Drop Error Vessel Section 7 Mid-Level Elevation Modeling Grid Heat Transfer Enhancement Calculation Revised Heat Transfer Multiplier Distributions Changes to Grid Blockage Ratio and Porosity Error in Burst Strain Application Code Uncertainty in BE LBLOCA Monte Carlo Simulations Error in Oxidation Calculations Support Column Unheated Conductor Error Vessel Average Temperature Uncertainty Numerical Ramp Entrained LiquidN apor Interfacial Drag Inappropriate Resetting of Transverse Liquid Mass Flow Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit Other

1.

None LICENSING BASIS PCT+ PCT ASSESSMENTS PCT=

Page 7 of 9 Serial No.20-219 Docket No. 50-395 0

0 0

0

-35 24 0

0 0

1961

Serial No.20-219 Docket No. 50-395 10 CFR 50.46 MARGIN UTILIZATION - BEST ESTIMATE LARGE BREAK COMPOSITE Plant Name:

V. C. Summer Utility Name:

Dominion Energy South Carolina Analysis Information EM:

CQD (1996)

Analysis Date:

Limiting Break Size:

February 2003 Westinghouse 1.7 DEGB Vendor:

FQ:

2.5 FdH:

Notes:

None LICENSING BASIS Analysis of Record PCT PCT ASSESSMENTS (Delta PCT)

A.

Prior ECCS Model Assessments

1.

Fan Cooler Performance Increase

2.

Improved Automation of End ofBlowdown Time

3.

Implementation of ASTRUM Capability in HOTSPOT 4

Revised Blowdown Heatup Uncertainty Distribution

5.

Revised Iteration Algorithm for Calculating The Average Fuel Temperature

6.

Improved Automation of End ofBlowdown Time

7.

Thermodynamic Properties from Thermo

8.

Pressurizer Fluid Volumes

9.

Vessel Unheated Conductor Nading

10.

Containment Relative Humidity Assumption

11.

HOTSPOT Fuel Relocation

12.

Steam Generator Nozzle Volume Accounting Error

13.

Cold Leg Volume Discrepancy

14.

Errors in Reactor Vessel Nozzle Data Collection

15.

HOTSPOT Burst Temperature Logic Errors

16.

V. C. Summer Upflow Conversion

17.

Zero Cross-Flow Boundary Condition Error

18.

Discrepancy in Metal Masses Used from Drawings

19.

HOTSPOT Gap Heat Transfer Logic

20.

HOTSPOT Statistical Output Logic

21.

Treatment of Vessel Average Temperature Uncertainty

22.

Additional Heat Sinks and Maximum Spray Flow

23.

Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Bumdown

24.

PAD 4.0 Implementation

25.

Zero Cross-Flow Boundary Condition Error

26.

HOTSPOT Burst Temperature Calculation For ZIRLO Cladding

27.

HOTSPOT Iteration Algorithm for Calculating The Initial Fuel Pellet Average Temperature

28.

WCOBRA/TRAC Automated Restart Process Logic Error

29.

Rod Internal Pressure Calculation

30.

WCOBRA/TRAC Thermal-Hydraulic History File Dimension used in HSDRIVER Page 8 of 9 Clad Temp{°F}

1988 2

0 0

5 0

0 0

-29 0

0 0

1 123

-118 0

0 0

0

B.

C.

D.

31.

32.

33.

34.

35.

36.

37.

38.

39.

40.

41.

42.

43.

44.

45.

46.

47.

48.

49.

50.

51.

52.

53.

Burst Elevation Selection Elevation for Heat Slab Temperature Initialization Heat Transfer Logic for Rod Burst Calculation WCOBRA/TRAC U19 File Dimension Error Correction Heat Transfer Model Error Corrections Correction to Heat Transfer Node Initialization Mass Conservation Error Fix Correction to Split Channel Momentum Equation Changes to Vessel Superheated Steam Properties Update to Metal Density Reference Temperatures Decay Heat Model Error Correction Correction to the Pipe Exit Pressure Drop Error Vessel Section 7 Mid-Level Elevation Modeling Grid Heat Transfer Enhancement Calculation Revised Heat Transfer Multiplier Distributions Changes to Grid Blockage Ratio and Porosity Error in Burst Strain Application Code Uncertainty in BE LBLOCA Monte Carlo Simulations Error in Oxidation Calculations Support Column Unheated Conductor Error Vessel Average Temperature Uncertainty Numerical Ramp Entrained LiquidNapor Interfacial Drag Inappropriate Resetting of Transverse Liquid Mass Flow Vapor Temperature Resetting Planned Plant Modification Evaluations

1.

None 2019 ECCS Model Assessments

1.

Removal of the Vessel Interfacial Heat Transfer Limit Other

1.

None LICENSING BASIS PCT+ PCT ASSESSMENTS PCT=

Page 9 of 9 Serial No.20-219 Docket No. 50-395 0

0 0

0

-35 24 0

0 0

1961

v t e Letter Sequence Request
EPID:L-2020-LLR-0039, ASME Section XI Inservice Inspection Program Proposed Inservice Inspection Alternative N1-I5-NDE-003 (Withdrawn, Closed)
Initiation Request, Request, Request, Request Acceptance, Acceptance Administration Questions Answers Results Withdrawal Other:
MONTHYEAR2020-04-07 [Table View]

ML20181A539

Text

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