ML041410260

ECCS Evaluation Model Revisions Annual Report

ML041410260
Person / Time
Site:	Summer
Issue date:	05/14/2004
From:	Byrne S South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML041410260 (23)

Text

Stephen A. Byrne Senior Vice President, Nuclear Operations 803.345.4622 A SCANA COMPANY May 14, 2004 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 ECCS EVALUATION MODEL REVISIONS ANNUAL REPORT Attached is the 2003 Emergency Core Cooling System (ECCS) Evaluation Model Revisions Annual Report for the Virgil C. Summer Nuclear Station (VCSNS). This report is being submitted pursuant to 1 OCFR50.46, which requires licensees to notify the NRC on at least an annual basis of corrections to or changes in the ECCS Evaluation Models.

Summary sheets describing changes and enhancements to the ECCS evaluation models for 2003 are included in Attachment I.

Peak Clad Temperature (PCT) sheets are included in Attachment II. All necessary revisions for any non-zero, non-discretionary, PCT change to Section C have been included. Any plant specific errors in the application of the model for 2003 will also be provided in Section C with discussion enclosed or cited.

If you have any questions, please call Mr. Arnie J. Cribb, Jr. at (803) 345-4346.

Very truly yours, Stephen A. Byrne AJC/SAB/dr Attachments c:

N. 0. Lorick K. M. Sutton N. S. Cams NRC Resident Inspector T. G. Eppink (w/o attachments)

NSRC R. J. White RTS (L-99-0152)

L. A. Reyes File (818.02-17, RR 8375)

K. R. Cotton DMS (RC-04-0072)

SCE&G I Virgil C. Summer Nudear Station. P. 0. Box 88. Jenkinsville, South Carolina 29065 T 1(803) 345.5209. www.stona.com

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 1 of 17 Changes and Enhancements to the ECCS Evaluation Models for 2003

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 2 of 17 Non-Discretionary Changes with PCT Impact NOTRUMP Bubble Rise/Drift Flux Model Inconsistencies Non-Discretionary Changes with No PCT Impact BART Quench Model Calculations BASHER Calculation of BASH Metal Heat Inputs Inconsistencies in Vessel Geometric Input Data LOCBART Fuel Rod Plenum Modeling LOCBART Grid Mass Balance NOTRUMP Drift Flux Model Inconsistencies NOTRUMP Inverted T-Node Sign Convention NOTRUMP Vapor Region Formation Logic SBLOCTA Burst Logic SBLOCTA ZIRLOTm Cladding Creep Constants Enhancements/Forward-Fit Discretionary Changes SATIMP/SPADES Updates SBLOCTA Oxide-to-Metal Ratio SBLOCTA Gap Conductance Model General Code Maintenance (Appendix K)

Document Control Desk Attachment I L-99-0152 RC-04-0072 Page 3 of 17 NOTRUMP BUBBLE RISE/DRIFT FLUX MODEL INCONSISTENCIES

Background

NOTRUMP was updated to resolve some inconsistencies in several drift flux models as well as the nodal bubble rise/droplet fall models. In summary, these changes include:

bubble rise and droplet fall model calculations were made consistent with flow link calculations. Corrections were made to limits employed in the vertical counter-current flooding models. Checking logic was added to correct situations where drift flux model inconsistencies could result (i.e. prevent liquid flow from an all-vapor node and vapor flow from all-liquid node). Also, a more rigorous version of the Yeh Drift Flux Model was implemented since the previous version of this model was incorrectly restricted to a 50%

void fraction limit. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect Representative plant calculations using the NOTRUMP code demonstrate that the implementation of these corrections leads to a bounding 350F increase of the calculated PCT for 10 CFR 50.46 purposes.

Plant Specific Text An evaluation was performed to identify PCT margin in previously assigned model assessment and safety evaluation PCT allocations. This evaluation was based on plant-specific calculations and current computer code versions. The evaluation demonstrated that there is conservatively 350F of available PCT margin in previously assigned model assessment and safety evaluation PCT allocations. Since 350F of margin is available to offset the 350F NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections PCT penalty, SPIKE calculations are not required and the previous Burst-and-Blockage

/ Time-in-Life PCT penalty remains applicable. The margin recovery benefit is reported in Section E.

- i

.4 Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 4 of 17 BART QUENCH MODEL CALCULATIONS

Background

BART is used to perform the core reflood heat transfer calculations in BASH and LOCBART. The BART portions of BASH and LOCBART were updated to resolve some minor logic problems that led to anomalous behavior in the quench model. These changes represent Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-1 3451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH Estimated Effect Sample BASH and LOCBART calculations demonstrated that these changes have either no effect or a negligible effect on the core inlet flooding rate and PCT and will be assigned a 0F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 5 of 17 BASHER CALCULATION OF BASH METAL HEAT INPUTS

Background

BASHER is used to generate the plant-specific input models for BASH. Some minor errors were discovered in the calculation of geometric terms used with the BASH metal heat model. As discussed below, it was determined that correcting these errors would have a negligible effect on results, so BASHER updates will be deferred to a future code release. When corrected, these changes will represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH Estimated Effect The changes described above are small and are considered to have a negligible effect on BASH results. These changes will be deferred to a future code release and are assigned a 0F PCT impact for 10 CFR50.46 reporting purposes.

Document Control Desk Attachment I L-99-0152 RC-04-0072 Page 6 of 17 INCONSISTENCIES IN VESSEL GEOMETRIC INPUT DATA

Background

Several inconsistencies were identified in the specification of vessel geometric data for plant-specific input models. These changes were evaluated for impacts on current licensing-basis analyses, and will be incorporated into the corresponding input databases on a forward-fit basis. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect A combination of sensitivity calculations and engineering evaluation led to the conclusion that the identified changes have a negligible effect on large and small break LOCA analysis results. These changes will therefore be assigned a 0F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 7 of 17 LOCBART FUEL ROD PLENUM MODELING

Background

A LOCBART calculation performed under non-standard conditions predicted burst to occur in the fuel rod plenum node. This situation does not occur for standard PWR licensing calculations, and is now precluded for all calculations by bypassing the burst calculations for the fuel rod plenum node..This change represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH Estimated Effect This situation does not occur for standard PWR licensing calculations and is assigned a 0F PCT effect for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-0152 RC-04-0072 Page 8 of 17 LOCBART GRID MASS BALANCE

Background

In the LOCBART spacer grid heat transfer model, a mass balance is applied to ensure that the available liquid can support the predicted wetting. Three discrepancies related to the grid mass balance in LOCBART were discovered and corrected, with a tendency for improved grid wetting in some instances. These changes represent a closely-related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-1 3451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH Estimated Effect Sample LOCBART calculations demonstrated that these changes have a negligible effect on PCT that will be assigned a 00F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 9 of 17 NOTRUMP DRIFT FLUX MODEL INCONSISTENCIES

Background

NOTRUMP was updated to resolve some inconsistencies in the resetting of certain parameters in the drift flux models when single phase conditions are determined to exist.

The previous coding had inadvertently omitted certain conditions on drift velocity and void fraction which are now included. Also, in the node boundary mixture level crossing logic, several partial derivatives for liquid and vapor volumetric fluxes with respect to mass flux in the void fraction model were erroneously set to zero. The correct partial derivative calculations were added to the code. In addition, several instances (stacking logic, accumulator empty logic and pump critical flow logic) where flow link specific volumes were incorrectly always based on saturated conditions were corrected. These changes represent a closely related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The subject changes involve logic that is seldom used in standard EM calculations. As such, the estimated effect on PCT calculations is 0F for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 10 of 17 NOTRUMP INVERTED T-NODE SIGN CONVENTION

Background

This change deals with the correction of the sign convention for inverted T-nodes, which was incorrectly applied via input into the EM. It can potentially impact the reactor vessel lower plenum node and the lower reactor coolant pump node in the standard EM. This change represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-1 3451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect This error affected the mixture/vapor interfacial area within a fluid node. Because these conditions only exist momentarily within the pump stack node and never in the reactor vessel lower plenum, it is judged that the impact of this error correction is insignificant.

Based on this judgment, coupled with the fact that plant model calculations show this to be the case, the correction of this error will be assigned a 0F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 11 of 17 NOTRUMP VAPOR REGION FORMATION LOGIC

Background

The logic governing formation of a vapor region within a fluid node in NOTRUMP was corrected to allow superheated conditions where appropriate, instead of saturated conditions which may not exist at that instant. This change represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-1 3451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect Typically, region formation conditions in standard EM calculations occur at saturation. If a region is formed at superheat conditions, the amount of superheat is usually small and the region quickly reaches saturated conditions. As such, the nature of these changes leads to an estimated PCT impact of 0F.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 12 of 17 SBLOCTA BURST LOGIC

Background

The burst logic in SBLOCTA was updated to preclude burst from occurring at more than one axial elevation on a given rod. This change represents a Non-Discretionary Change in accordance with Section 4.1.2 of WCAP-13451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect Most SBLOCTA calculations predict burst at no more than one axial elevation per rod and are therefore unaffected by this discrepancy. For the affected cases, SBLOCTA calculations and/or engineering evaluation led to the conclusion that resolving the discrepancy would not produce an increase in the limiting PCT. This change is therefore assigned a 00F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-0152 RC-04-0072 Page 13 of 17 SBLOCTA ZIRLOTM CLADDING CREEP CONSTANTS

Background

SBLOCTA was updated to correct two of the constants in the high-temperature creep model for ZIRLO cladding, which were found to disagree with the basis documentation. These changes represent a closely related group of Non-Discretionary Changes in accordance with Section 4.1.2 of WCAP-1 3451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The changes identified above lead to a small change in the creep rate over a limited range of temperatures, which is considered to have a negligible effect on results and will be assigned a 00F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 14 of 17 SATIMP/SPADES UPDATES

Background

SATIMP and SPADES are used to generate the plant-specific input models for SATAN-VI and NOTRUMP, respectively. Some minor improvements were made to SATIMP and SPADES, primarily to provide more rigorous calculations of certain SATAN-VI and NOTRUMP inputs. An example of these changes is to replace linear interpolation with parabolic interpolation in the SATIMP calculation of the reactor coolant pump head at steady-state operating conditions. These changes represent Discretionary Changes that will be implemented on a forward-fit basis, in accordance with Section 4.1.1 of WCAP-1 3451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The nature of these changes leads to an estimated PCT effect of 0F for both large and small break LOCA.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 15 of 17 SBLOCTA OXIDE-TO-METAL RATIO

Background

An option has been added to SBLOCTA to allow conversion of the user-specified zirconium-oxide thickness into equivalent cladding reacted. This adjustment is made during problem initialization, and the cladding outside diameter is modified accordingly.

This change represents a Discretionary Change that will be implemented on a forward-fit basis, in accordance with Section 4.1.1 of WCAP-13451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect A sample SBLOCTA calculation showed that this change has a minimal effect on PCT.

This change will be implemented on a forward-fit basis and will be assigned a 00F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 16 of 17 SBLOCTA GAP CONDUCTANCE MODEL

Background

The convective term in the SBLOCTA pellet-to-cladding gap conductance model was updated for consistency with the corresponding model in LOCBART. Included in this change is the implementation of a PAD-version-specific value of the gap reduction factor, which is specified by the user in the SBLOCTA input file. This change represents a Discretionary Change that will be implemented on a forward-fit basis, in accordance with Section 4.1.1 of WCAP-1 3451.

Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect Sample SBLOCTA calculations showed that this change has a negligible effect on PCT.

This change will be implemented on a forward-fit basis and will be assigned a 00F PCT impact for 10 CFR 50.46 reporting purposes.

Document Control Desk Attachment I L-99-01 52 RC-04-0072 Page 17 of 17 GENERAL CODE MAINTENANCE (APPENDIX K)

Background

Various changes in code input and output format have been made to enhance usability and help preclude errors in analyses. This includes both input changes (e.g., more relevant input variables defined and more common input values used as defaults) and input diagnostics designed to preclude unreasonable values from being used, as well as various changes to code output which have no effect on calculated results. In addition, various blocks of coding were rewritten to eliminate inactive coding, optimize the active coding, and improve commenting, both for enhanced usability and to facilitate code debugging when necessary. These changes represent Discretionary Changes that will be implemented on a forward-fit basis, in accordance with Section 4.1.1 of WCAP-13451.

Affected Evaluation Models 1981 Westinghouse Large Break LOCA Evaluation Model with BASH 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The nature of these changes leads to an estimated PCT impact of 00F.

Document Control Desk Attachment II L-99-01 52 RC-04-0072 Page 1 of 5 LOCA PCT Sheets for Virgil C. Summer Nuclear Station

Document Control Desk Attachment II L-99-01 52 RC-04-0072 Page 2 of 5 Westinghouse LOCA Peak Clad Temperature Summary for Large Break Plant Name:

V. C. Summer Utility Name:

South Carolina Electric & Gas Revision Date:

3/3/04 Analysis Information EM:

BASH Analysis Date:

10/1/95 Limiting Break Size:

Cd = 0.4 FQ:

2.4 FdH:

1.62 Fuel:

Vantage +

SGTP (/6):

10 Notes:

Analysis-Of-Record was done with FQ=2.50 and FdH = 1.70.

Clad Temp (0F)

Ref.

Notes LICENSING BASIS Analysis-Of-Record PCT 2099 1

(a)

MARGIN ALLOCATIONS (Delta PCT)

A. PRIOR PERMANENT ECCS MODEL ASSESSMENTS 1.

Si Error Reanalysis

-90 2

(a,b)

2.

Accumulator Line/Pressurzer Surge Line Data, LOCBART Spacer Grid 153 2

(a,c)

Single-Phase Heat Transfer Error, LOCBART Zirc-Water Oxidation Error, and Reanalysis of Limiting AOR Case

3.

LOCBART Vapor Film Flow Regime Heat Transfer Error

-15 3

4.

LOCBART Cladding Emissivity Errors

-10 4

5.

LOCBART ZIRLOTm Cladding Specific Heat Model 40 5

6.

PAD 4.0 Initial Pellet Temperatures

-40 5

B. PLANNED PLANT CHANGE EVALUATIONS

1.

None 0

C. 2003 PERMANENT ECCS MODEL ASSESSMENTS

1.

None 0

D. TEMPORARY ECCS MODEL ISSUES

1.

None 0

E. OTHER

1.

None 0

LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =

2137

References:

1.

CGE-95-0009-SGUL, 'Revised Large Break LOCA Results for Uprating Submittal,' October 24,1995.

2.

CGE-99-044, 'South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 10 CFR 50.46 BART/BASH Evaluation Model, Mid-Year Notification and Reporting for 1999,' September 17, 1999.

3.

CGE-00-044, "South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 10 CFR 50.46 Appendix K (BART/BASH/NOTRUMP) Evaluation Model, Mid-Year Notification and Reporting for 2000'. June 30,2000.

4.

CGE-00-1 12, 'South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 10 CFR 50.46 BART/BASH Evaluation Model Mid-Year Notification and Reporting for 2000,' December 2000.

Document Control Desk Attachment II L-99-01 52 RC-04-0072 Page 3 of 5 Westinghouse LOCA Peak Clad Temperature Summary for Large Break Plant Name:

V. C. Summer Utility Name:

South Carolina Electric & Gas Revision Date:

3/3/04

5.

CGE-03-12, "10CFR 50.46 Annual Notification and Reporting for 2002,' March 2003.

Notes:

(a) Analysis was done for Delta-75 steam generators and core power at 2900 MWt.

(b) This plant specific reanalysis addressed the correction of Safety Injection Performance Inputs. These results incorporate the SATAN/LOCTA Fluid Conditions Translation Error and the Accumulator Pressure and Water Volume Uncertainties evaluation, so these PCT penalties are no longer applicable. IFBA fuel Is limiting compared to non-I FBA fuel.

(c) This reanalysis was based on the SI Error reanalysis; modelled a reduction In FO from 2.5 to 2.4, a reduction In FdH from 1.70 to 1.62, and a reduction In P-bar-HA from 1.514 to 1.443; and addressed the following Issues:

Accumulator Line/Pressurizer Surge Une Data, LOCBART Spacer Grid Single-Phase Heat Transfer Error, and LOCBART Zirc-Water Oxidation Error. IFBA fuel Is limiting compared to non-IFBA fuel.

Document Control Desk Attachment II L-99-01 52 RC-04-0072 Page 4 of 5 Westinghouse LOCA Peak Clad Temperature Summary for Small Break Plant Name:

Utility Name:

Revision Date:

V. C. Summer South Carolina Electric & Gas 3/3/04 Analysis Information EM:

NOTRUMP Analysis Date:

2/1/94 Limiting Break Size:

2 inch FO:

2.4 FdH:

1.62 Fuel:

Vantage +

SGTP (%):

10 Notes:

Limiting Break Size shifted from 2 inch to 3 inch (b,d) and FQ reduced from 2.45 to 2.40 (f)

Clad Temp (0F)

Ref.

Notes LICENSING BASIS Analysis-Of-Record PCT 1823 1

(a)

MARGIN ALLOCATIONS (Delta PCT)

A.

PRIOR PERMANENT ECCS MODEL ASSESSMENTS

1.

LUCIFER Error Corrections

2.

Effect of Si In Broken Loop

3.

Effect of Improved Condensation Model

4.

Axial Nodalization, RIP Model Revision and SBLOCTA Error Corrections Analysis

5.

Boiling Heat Transfer Correlation Error

6.

Steam Line Isolation Logic Error

7.

NOTRUMP Specific Enthalpy Error

8.

SALIBRARY Double Precision Error

9.

SBLOCTA Fuel Rod Initialization Error

10.

NOTRUMP Mixture Level Tracking / Region Depletion Errors B. PLANNED PLANT CHANGE EVALUATIONS 1.

Increased Accumulator Pressure and Water Volume Uncertainties

2.

Annular Blankets 3.

Main Feedwater Temperature Increase Evaluation C. 2003 PERMANENT ECCS MODEL ASSESSMENTS 1.

NOTRUMP Bubble Rise / Drift Flux Model Inconsistency Corrections D. TEMPORARY ECCS MODEL ISSUES

1.

None

-16 150

-150 96

-6 18 20

-15 10 13 34 10 0

3 3

3 4

5 6

6 6

7 9

2 2

10 (b) 35 12 0

E. OTHER 1.

2.

3.

4.

Burst and Blockage/Tme in Ufe Margin Recovery (SI Performance Inputs Evaluation)

GEDM Evaluation Analysis Margin 245

-36 0

-35 9

8 11 12 (c,e)

(d)

(f)

LICENSING BASIS PCT + MARGIN ALLOCATIONS PCT =

2196

J Document Control Desk 1 L-99-01 52 RC-04-0072 Page 5 of 5 Westinghouse LOCA Peak Clad Temperature Summary for Small Break Plant Name:

V. C. Summer Utility Name:

South Carolina Electric & Gas Revision Date:

3/3/04

References:

1.

CGE-93-0054-SGUL, *SECL-93-036, Rev. 1," March 9, 1994.

2.

CGE-99-008. 'South Carolina Electric and Gas Company, Virgil C. Summer Station,1 0 CFR 50.46 Annual Notification and Reporting for 1998," March 5, 1999.

3.

CGE-94-205, 'South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Notification and Reporting Information.' February 8, 1994.

4.

CGE-94-228, 'South Carolina Electric and Gas Company, Virgil C. Summer Station, SBLOCTA Axial Nodalization," October 27, 1994.

5.

CGE-95-201, 'South Carolina Electric and Gas Company, Virgil C. Summer Station, 1 0 CFR 50.46 Notification and Reporting Information," February 3, 1995.

6.

CGE-96-202, 'South Carolina Electric and Gas Company, Virgil C. Summer Station, 1 0 CFR 50.46 Annual Notification and Reporting." February 9, 1996.

7.

CGE-96-213, 'South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Small Break LOCA Notification and Reporting," July 8, 1996.

8.

CGE-00-006, 'South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 10 CFR 50.46 Annual Notification and Reporting for 1999," February 25, 2000.

9.

CGE-00-044, "South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 1 0 CFR 50.46 Appendix K (BART / BASH / NOTRUMP) Evaluation Model, Mid-Year Notification and Reporting for 2000," June 30, 2000.

10.

CGE-00-063, 'Safety Evaluation for Increased Main Feedwater Temperature (SECL-00-1 1 8)," August 25, 2000.

11.

CAB-02-64/NF-CG-02-16, "Cycle 14 Reload Safety Evaluation," March 2002.

12.

CGE-03-80, "10 CFR 50.46 Mid-Year Notification and Reporting for 2003," January 2004.

Notes:

(a)

AOR performed for core power = 2900 MWt and Delta-75 steam generators.

(b) The SBLOCA evaluation for Increased accumulator pressure and water volume uncertainties causes the limiting break equivalent diameter to shift from 2-Inch to 3-Inch. The 340F value does not Include the effect on SBLOCA burst/blockage behavior.

(c)

This assessment Is a function of base PCT plus margin allocation and as such will Increase/decrease with margin allocation changes.

(d) The Margin Recovery (SI Performance Evaluation) resulted In a 36 OF PCT benefit. Note that the evaluation considered the 2 Inch and 3 Inch break and resulted In the limiting break equivalent diameter to remain shifted from 2 Inch to 3 inch.

(e) Value Includes previous Burst and Blockage I Time In Life penalty SPIKE Correlation Revision penalty (1999 Annual Report), and consideration of a new penalty due to Item C.1 (NOTRUMP Mixture Level Tracking / Region Depletion.

(f)

The reduced AOR GEDMs have been violated during the CGE Cycle 14 Reload Process. An evaluation was performed using default GEDMs and taking credit for a lower PHA of 1.42 and FQ of 2.40. Analysis-of-record was done with FO=2.45 and PHA=1.443. The evaluation concluded a net zero PCT effect to the Small Break LOCA Analysis.