View source for RC-16-0094, (VCSNS) Unit 1 - 2015 ECCS Evaluation Model Revisions Report

{{Adams
| number = ML16173A299
| issue date = 06/16/2016
| title = (VCSNS) Unit 1 - 2015 ECCS Evaluation Model Revisions Report
| author name = Lippard G
| author affiliation = SCANA Corp, South Carolina Electric &amp; Gas Co
| addressee name = 
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000395
| license number = NPF-012
| contact person = 
| case reference number = LTD 321, RC-16-0094
| document type = Annual Report, Letter type:RC
| page count = 14
}}

=Text=
{{#Wiki_filter:George A. Lippard Vice President, Nuclear Operations 803.345.4810 June 16, 2016 A SC!JNA COMPANY Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555

==Dear Sir I Madam:==

==Subject:==
VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ECCS EVALUATION MODEL REVISIONS REPORT South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority, hereby submits the 2015 Emergency Core Cooling System (ECCS) Evaluation Model Revisions Annual Report for VCSNS. *This report is being submitted pursuant to 10 CFR 50.46, 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 2015 are included in Attachment I. Peak Clad Temperature (PCT) Rackup Sheets are included in Attachment II.
If you have any questions, please call Bruce L. Thompson at (803) 931-5042.
Very truly yours, George A. Lippard TS/GAL/wm Attachments c:    K. B. Marsh                                                                               S. A. Williams S. A. Byrne                                                                                NRC Resident Inspector J.B. Archie                                                                                K. M. Sutton N. s: Carns                                                                                NSRC J. H. Hamilton                                                                             RTS {LTD 321, RR 8375)
J. W. Williams                                                                             File       (818.02-17)
W. M. Cherry                                                                               PRSF (RC-16-0094)
C. Haney V. C. Summer Nuclear Station* P. 0. Box 88
* Jenkinsville, SC* 29065
* F(803) 941-9776

Document Control Desk Attachment I LTD 321 RC-16-0094 Page 1 of 2 Attachment I Changes and Enhancements to the ECCS Evaluation Models for 2015

Document Control Desk Attachment I LTD 321 RC-16-0094 Page 2 of 2 GENERAL CODE MAINTENANCE

===Background===
Various changes have been made to enhance the usability of codes and to streamline future analyses. Examples of these changes include modifying input variable definitions, units and defaults; 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.
Affected Evaluation Models 1985 Westinghouse Small Break LOCA Evaluation Model with NOTRUMP Estimated Effect The nature of these changes leads to an estimated Peak Cladding Temperature (PCT) impact of 0&deg;F.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 1 of 11 Attachment II Peak Clad Temperature (PCT) Rackup Sheets

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 2of11 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:          V. C. Summer Utility Name:        South Carolina Electric & Gas Revision Date: 2/1/2016                                                    Composite Analysis    Information EM:           CQD (1996)          Analysis Date:     2/3/2003 Limiting Break Size:    Guillotine FQ:           2.5                 FdH:           1.7 Fuel:         Vantage +           SGTP (%):      10 Notes:        Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt
                                                                 *Clad Temp (&deg;F)   Ref. Notes LICENSING BASIS Analysis-Of-Record PCT                                            1988      1 PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
: 1. Backfit Through 2001 Reporting Year                         0     2
: 2. Revised Slowdown Heatup Uncertainty Distribution             5     3
: 3. PAD 4.0 Implementation                                    -118     6
: 4. Evaluation of Fuel Pellet Thermal Conductivity             123     6        (a)
Degradation and Peaking Factor Burndown
: 5. Transverse Momentum Cells for Zero                           0     6         (b)
Cross-flow Boundary Condition Error
: 6. Revised Heat Transfer Multiplier Distributions             -35     7
: 7. Changes to Grid Blockage Ratio and Porosity                 24     8
: 8. Error in Burst Strain Application                            0     9 B. PLANNED PLANT MODIFICATION EVALUATIONS
: 1. Fan Cooler Performance Increase                             2     2
: 2. Upflow Conversion EvalLJ.~tion                             -29     4
: 3. Additional Heat Sinks and Increased Spray Flow Rate          1     5 C. 2015 ECCS MODEL ASSESSMENTS
: 1. None                                                        0 D.OTHER
: 1. None                                                        0 LICENSING BASIS PCT + PCT ASSESSMENTS                      PCT=     1961 References
: 1. WCAP-16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C. Summer Nuclear Station," June 2003.
: 2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.
: 3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
: 4. L TR-LIS-08-578, Revision 2, "10 CFR 50.46 Reports for the V. C. Summer (CGE)
Upflow Conversion Large Break LOCA Evaluation and Assessment of Transverse Momentum Cells with a Zero Cross-flow Boundary Condition Error," January 2009.
: 5. CGE-10-29, "BELOCA Summary Report," November 2010.
: 6. LTR-LIS-12-372, "V. C. Summer, 10 CFR 50.46 Notification and Reporting for Fuel

Document Control Desk 1 LTD 321 RC-16-0094 Page 3 of 11 Pellet Thermal Conductivity Degradation and Peaking Factor Burndown,"
September 20, 2012.
: 7. LTR-LIS-13-353, "V. C. Summer 10 CFR 50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
: 8. LTR-LIS-13-476, "V. C. Summer 10 CFR 50.46 Report for Changes to Grid Blockage Ratio and Porosity," October 2013.
: 9. LTR-LIS-14-37, "V. C. Summer 10 CFR 50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.
Notes:
(a) This evaluation credits peaking factor burndown; see Reference 6.
(b) This input error was originally reported in Reference 4. That evaluation is superseded by the report in Reference 6.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 4 of 11 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:         V. C. Summer Utility Name:       South Carolina Electric & Gas Revision Date: 2/1/2016                                                    Slowdown Analysis    Information EM:          CQD (1996)          Analysis Date:      2/3/2003 Limiting Break Size:    Guillotine FQ:          2.5                 FdH:            1.7 Fuel:        Vantage +           SGTP (%):       10 Notes:       Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Clad Temp (&deg;F)   Ref. Notes LICENSING BASIS Analysis-Of-Record PCT                                            1860      1 PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
: 1. Backfit Through 2001 Reporting Year                           0    2
: 2. Revised Slowdown Heatup Uncertainty Distribution            49     3
: 3. PAD 4.0 Implementation                                     -83     6
: 4. Evaluation of Fuel Pellet Thermal Conductivity                0    6         (a)
Degradation and Peaking Factor Burndown
: 5. Transverse Momentum Cells for Zero Cross-flow                 0    6         (b)
Boundary Condition Error
: 6. Revised Heat Transfer Multiplier Distributions              -5     7
: 7. Changes to Grid Blockage Ratio and Porosity                   0    8
: 8. Error in Burst Strain Application                             0    9 B. PLANNED PLANT MODIFICATION EVALUATIONS
: 1. Fan Cooler Performance Increase                               0    2
: 2. Upflow Conversion Evaluation                                ,.7    4
: 3. Additional Heat Sinks and Increased Spray Flow Rate           0    5 C. 2015 ECCS MODEL ASSESSMENTS
: 1. None                                                          0 D.OTHER
: 1. None                                                          0 LICENSING BASIS PCT + PCT ASSESSMENTS                      PCT=    1814 References
: 1. WCAP-16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C. Summer Nuclear Station," June 2003.
: 2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.
: 3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
: 4. LTR-LIS-08-578, Revision 2, "10 CFR 50.46 Reports for the V. C. Summer (CGE)
Upflow Conversion Large Break LOCA Evaluation and Assessment of Transverse Momentum Cells with a Zero Cross-flow Boundary Condition Error," January 2009.
: 5. CGE-10-29, "BELOCA Summary Report," November 2010.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 5of11
: 6. LTR-LIS-12-372, "V. C. Summer, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Burndown," September 20, 2012.
: 7. LTR-LIS-13-353, "V. C. Summer 10 CFR 50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
: 8. LTR-LIS-13-476, "V. C. Summer 10 CFR 50.46 Report for Changes to Grid Blockage Ratio and Porosity," October 2013.
: 9. LTR-LIS-14-37, "V. C. Summer 10 CFR 50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.
Notes:
(a) This evaluation credits peaking factor burndown, see Reference 6.
(b) This input error was* originally reported in Reference 4. That evaluation is superseded by the report in Reference 6.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 6of11 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:         V. C. Summer Utility Name:       South Carolina Electric & Gas Revision Date: 2/1/2016                                                       Reflood 1 Analysis    Information EM:           CQD (1996)         Analysis Date:      2/3/2003 Limiting Break Size:    GL1illotine FQ:          2.5                 FdH:            1.7 Fuel:        Vantage +           SGTP (%):       10 Notes:       Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Clad Temp (&deg;F)   Ref. Notes LICENSING BASIS Analysis-Of-Record PCT                                            1808      1 PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
: 1. Backfit Through 2001 Reporting Year                          0     2
: 2. Revised Slowdown Heatup Uncertainty Distribution             5     3
: 3. PAD 4.0 Implementation                                   -118      6
: 4. Evaluation of Fuel Pellet Thermal Conductivity            113      6         (a)
Degradation and Peaking Factor Burndown
: 5. Transverse Momentum Cells for Zero Cross-flow                0     6         (b)
Boundary Condition Error
: 6. Revised Heat Transfer Multiplier Distributions               5     7
            . 7. Changes to Grid Blockage Ratio and Porosity                 24     8
: 8. Error in Burst Strain Application                           20     9 B. PLANNED PLANT MODIFICATION EVALUATIONS
: 1. Fan Cooler Performance Increase                              1     2
: 2. Upflow Conversion Evaluation                               -44     4
: 3. Additional Heat Sinks and Increased Spray Flow Rate          0     5 C. 2015 ECCS MODEL ASSESSMENTS
: 1. None                                                         0 D.OTHER
: 1. None                                                         0 LICENSING BASIS PCT + PCT ASSESSMENTS                      PCT=    1814 References
: 1. WCAP-16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C. Summer Nuclear Station," June 2003.
: 2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.
: 3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
: 4. LTR-LIS-08-578, Revision 2, "10 CFR 50.46 Reports for the V. C. Summer (CGE)
Upflow Conversion Large Break LOCA Evaluation and Assessment of Transverse Momentum Cells with a Zero Cross-flow Boundary Condition Error," January 2009.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 7of11
: 5. CGE-10-29, "BELOCA Summary Report," November 2010.
: 6. LTR-LIS-12-372, "V. C. Summer, 10 CFR 50.46 Notification and Reporting for Fuel Pellet Thermal Conductivity Degradation and Peaking Factor Burndown," September 20, 2012.
: 7. LTR-LIS-13-353, "V. C. Summer 10 CFR 50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
: 8. LTR-LIS-13-476, "V. C. Summer 10 CFR 50.46 Report for Changes to Grid Blockage Ratio and Porosity," October 2013.
: 9. LTR-LIS-14-37, "V. C. Summer 10 CFR 50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.
Notes:
(a) This evaluation credits peaking factor burndown, see Reference 6.
(b) This input error was originally reported in Reference 4. That evaluation is superseded by the report in Reference 6.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 8of11 Westinghouse LOCA Peak Clad Temperature Summary for Best Estimate Large Break Plant Name:        V. C. Summer Utility Name:      South Carolina Electric & Gas Revision Date: 2/1/2016                                                        Reflood 2 Analysis   Information EM:         CQD (1996)          Analysis Date:      2/3/2003   Limiting Break Size:    Guillotine FQ:         2.5                 FdH:            1.7 Fuel:       Vantage +           SGTP (%):       10 Notes:      Delta 75 Replacement Steam Generator Uprate Core Power 2900 MWt Clad Temp (&deg;F)    Ref. Notes LICENSING BASIS Analysis-Of-Record PCT                                             1988 . 1 PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
: 1. Backfit Through 2001 Reporting Year                             0    2
: 2. Revised Slowdown Heatup Uncertainty Distribution                5    3
: 3. PAD 4.0 Implementation                                      -118     6
: 4. Evaluation of Fuel Pellet Thermal Conductivity               123     6         (a)
Degradation and Peaking Factor Burndown
: 5. Transverse Momentum Cells for Zero Cross-flow                   0    6         (b)
Boundary Condition Error
: 6. Revised Heat Transfer Multiplier Distributions               -35     7
: 7. Changes to Grid Blockage Ratio and Porosity                    24    8
: 8. Error in Burst Strain Application                               0    9 B. PLANNED PLANT MODIFICATION EVALUATIONS
: 1. Fan Cooler Performance Increase                                 2    2
: 2. Upflow Conversion Evaluation                                  -29    4
: 3. Additional Heat Sinks and Increased Spray Flow Rate             1    5 C. 2015 ECCS MODEL ASSESSMENTS
: 1. None                                                            0 D.OTHER
: 1. None                                                           0 LICENSING BASIS PCT + PCT ASSESSMENTS                       PCT=     1961 References
: 1. WCAP-16043, "Best Estimate Analysis of the Large Break Loss of Coolant Accident for the Virgil C. Summer Nuclear Station," June 2003.
: 2. CGE-03-12, "10 CFR 50.46 Annual Notification and Reporting for 2002," March 2003.
: 3. CGE-05-20, "10 CFR 50.46 Annual Notification and Reporting for 2004," April 2005.
: 4. LTR-LIS-08-578, Revision 2, "10 CFR 50.46 Reports for the V. C. Summer (CGE)
Upflow Conversion Large Break LOCA Evaluation and Assessment of Transverse Momentum Cells with a Zero Cross-flow Boundary Condition Error," January 2009.
: 5. CGE-10-29, "BELOCA Summary Report," November 2010.
: 6. LTR-LIS-12-372, "V. C. Summer, 10 CFR 50.46 Notification and Reporting for Fuel

Document Control Desk 1 LTD 321 RC-16-0094 Page 9of11 Pellet Thermal Conductivity Degradation and Peaking Factor Burndown," September 20, 2012.
: 7. LTR-LIS-13-353, "V. C. Summer 10 CFR 50.46 Report for Revised Heat Transfer Multiplier Distributions," July 2013.
: 8. LTR-LIS-13-476, "V. C. Summer 10 CFR 50.46 Report for Changes to Grid Blockage Ratio and Porosity," October 2013.
: 9. LTR-LIS-14-37, "V. C. Summer 10 CFR 50.46 Report for the HOTSPOT Burst Strain Error Correction," January 2014.
Notes:
(a) This evaluation credits peaking factor burndown, see Reference 6.
(b) This input error was originally reported in Reference 4. That evaluation is superseded by the report in Reference 6.

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 10of11 Westinghouse LOCA Peak Clad Temperature Summary for Appendix K Small Break Plant Name:          V. C. Summer Utility Name:        South Carolina Electric & Gas Revision Date: 2/1/2016 Analysis     Information EM:            NOTRUMP            Analysis Date:    9/12/2006 Limiting Break Size:       31nch FQ:            2.45               FdH:              1.62 Fuel:         Vantage+            SGTP (%):         10 Notes:
Clad Temp (&deg;F)   Ref. Notes LICENSING BASIS Analysis-Of-Record PCT                                             1775       9       (a)
PCT ASSESSMENTS (Delta PCT)
A. PRIOR ECCS MODEL ASSESSMENTS
: 1. None                                                         0 B. PLANNED PLANT MODIFICATION EVALUATIONS
: 1. Upflow Conversion                                          148    10, 11 C. 2015 ECCS MODEL ASSESSMENTS
: 1. None                                                         0 D.OTHER
: 1. None                                                         0 LICENSING BASIS PCT + PCT ASSESSMENTS                       PCT=     1923 References
: 1. CGE-94-205, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Notification and Reporting Information," February 8, 1994.
: 2. CGE-94-228, "South Carolina Electric and Gas Company, Virgil C. Summer Station, SBLOCTA Axial Nodalization," October 27, 1994.
: 3. CGE-95-201, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Notification and Reporting Information," February 3, 1995.
* 4. CGE-96-202, "South Carolina Electric and Gas Company, Virgil C. Summer Station, 10 CFR 50.46 Annual Notification and Reporting," February 9, 1996.
: 5. 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.
: 6. CGE-00-044, "South Carolina Electric and Gas Company, Virgil C. Summer Nuclear Station, 10 CFR 50.46 Appendix K (BART I BASH I NOTRUMP) Evaluation Model, Mid-Year Notification and Reporting for 2000," June 30, 2000.
: 7. CGE-03-80, "10 CFR 50.46 Mid-Year Notification and Reporting for 2003,"
January 2004.
* 8, LTR-LIS-06-344, "Transmittal of Updated V. C. Summer SBLOCA PCT Rackup Sheets," November 2006.
: 9. LTR-LIS-06-662, Transmittal of V. C. Summer SBLOCTA PCT Rackup Sheets for HHSI Throttle Valve Replacement," November 2006.
: 10. WCAP-16980-P, Revision 1, "Reactor Internals Upflow Conversion Program

Document Control Desk Attachment II LTD 321 RC-16-0094 Page 11 of 11 Engineering Report V. C. Summer Nuclear Station Unit 1," December 2008.
: 11. LTR-LIS-09-18, "10 CFR 50.46 Report for the V. C. Summer (CGE) Upflow Conversion Program Small Break LOCA Evaluation," January 2009.
Notes:
(a) The Rebaseline Analysis includes the impacts of the following model assessments:
1-LUCIFER Error Corrections (Ref. 1) 2-Effect of SI in Broken Loop (Ref. 1) 3-Effect of Improved Condensation Model (Ref. 1) 4-Axial Nodalization, RIP Model Revision and SBLOCTA Error Corrections Analysis (Ref. 2) 5-Boiling Heat Transfer Error (Ref. 3) 6-Steam Line Isolation Logic Error (Ref. 3) 7-NOTRUMP Specific Enthalpy Error (Ref. 4) 8-SALIBRARY Double Precision Error (Ref. 4) 9-SBLOCTA Fuel Rod Initialization Error (Ref. 5) 10-NOTRUMP Mixture Level Tracking I Region Depletion Errors (Ref. 6) 11-NOTRUMP Bubble Rise I Drift Flux Model Inconsistency Corrections (Ref. 7) 12-Refined Break Spectrum (Ref. 8) 13-High head safety injection (HHSI) flow increase (Ref. 9)}}