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| {{#Wiki_filter:}} | | {{#Wiki_filter:Nuclear Operating Company South Texas Pro/ect Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483 September 25, 2017 NOC-AE-17003520 10CFR50.59 STI: 34543702 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.59 Summary Report Pursuant to the requirements of 10CFR50.59, the attached report contains a brief description and summary of the 10CFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project from October 2015 through September 2017. |
| | There are no commitments in this letter. |
| | If there are any questions regarding this summary report, please contact K. A. Van Daalen at (361) 972-8030 or me at (361) 972-8164. |
| | ( |
| | Michael P. Murray Manager, Regulatory Affairs kav |
| | |
| | ==Attachment:== |
| | 10CFR50.59 Evaluation Summaries October 2015 - September 2017 |
| | |
| | NOC-AE-17003520 Page 2 of 2 ec: |
| | (paper copy) (electronic copy) |
| | Morgan, Lewis & Bockius LLP Regional Administrator, Region IV Steve Frantz, Esquire U. S. Nuclear Regulatory Commission Paul Bessette 1600 East Lamar Boulevard Arlington, TX 76011-4511 D. S. Nuclear Regulatory Comm iss io n Lisa M. Regner NRG South Texas LP Lisa M. Regner Mark Walker Senior Licensing Project Manager Jim von Suskil U.S. Nuclear Regulatory Commission Skip Zahn One White Flint North (08H04) 11555RockvillePike CPS Energy Rockville, MD 20852 Kevin Polio Cris Eugster L. D. Blaylock NRC Resident Inspector U. S. Nuclear Regulatory Commission CjtyofAustin P. 0. Box 289, Mail Code: MN116 Elaina Ball Wadsworth,TX 77483 John Wester Texas Department of State Health Services Helen Watkins Robert Free |
| | |
| | NOC-AE-17003520 Attachment Page 1 of 3 10CFR50.59 Evaluation Summaries October 2015 - September 2017 Summaries of the following 10CFR50.59 Evaluations are provided in this attachment: |
| | No. Condition Report Subject Number |
| | : 1. 14-8780-308 Apply In-Situ "Normalized" Calibration Values to Main Feedwater flow Transmitters |
| | : 2. 16-2197-15 Manual Operator Load Shed of Additional Class 1E Battery Loads during Loss of All AC Power |
| | : 3. 14-12285-20 Modify Use ofWRB-2M DNB Correlation in UFSAR Accident Analyses |
| | |
| | NOC-AE-17003520 Attachment Page 2 of 3 14-8780-308: Apply In-Situ "Normalized" Calibration Values to Main Feedwater flow Transmitters |
| | |
| | == Description:== |
| | The subject of this Evaluation is the application of in-situ developed correction factors to the existing main feedwater flow transmitter scaling values initially based on the venturi flow element test laboratory results. |
| | Summary: The proposed activity involves the application of a correction factor to the existing feedwater flow transmitter scaling values initially developed based on the venturi flow element test laboratory test results and replacing these scaling values with feedwater flow transmitter scaling values corrected to match the LEFM Cameron Caldon Check Plus system measured flow. Application of these in-situ obtained scaling values represents a change in methodology as originally established for the STP 1.4% Power Uprate by application of Westinghouse WCAP-15697 and approved by the NRC for plant operation where the ultrasonic flow measurement instrumentation is out of service for greater than 72 hours resulting in feedwater flow measured by venturi flow element based instrumentation. This evaluation shows that the results of the revised methodology are the same as, or more conservative than, the methodology being replaced. |
| | The evaluation determined that prior NRC approval was not required. |
| | 16-2197-15: Manual Operator Load Shed of Additional Class 1 E Battery Loads during Loss of All AC Power |
| | |
| | == |
| | Description:== |
| | The subject of this Evaluation is to revise the procedure for loss of all AC power as a result of a revision to Electrical Calculation 13DJ006, "125 VDC Battery Four Hour Coping Analysis." |
| | Summary: The proposed activity involves revising STP procedure OPOP05-EO-ECOO, "Loss of All AC Power," such that an STP operator manually sheds additional Class IE battery loads during a loss of all AC power event. Currently, the subject STP procedure requires an STP operator to manually load shed ESF Load SequencerA, B and C within 30 minutes of a loss of all AC power event. In addition to this procedure step, this change involves revising the subject procedure such that STP operators also manually load shed seven additional loads and ensure five other loads remain "ON" (not load shed) on DP1201 within 30 minutes of a loss of all AC power event. This procedure change is a result of a revision to Electrical Calculation 13DJ006, "125 VDC Battery Four Hour Coping Analysis." |
| | The evaluation determined that prior NRC approval was not required. |
| | |
| | NOC-AE-17003520 Attachment Page 3 of 3 |
| | : 3. 14-12285-20: Modify Use ofWRB-2M DNB Correlation in UFSAR Accident Analyses |
| | |
| | == Description:== |
| | The subject of this Evaluation is to modify the use of the WRB-2M DNB Correlation in UFSAR Accident Analyses. |
| | Summary: The change applies a conservative penalty when using the WRB-2M correlation to determine the departure from nucleate boiling (DNB) in the fuel. The penalty is applied when the fluid conditions are calculated to be in the non-conservative steam quality region of the range of applicability of the WRB-2M correlation limit described in UFSAR Section 4.4.2.2.1. The use of the penalty does not impact the WRB-2M correlation or the approved range of applicability given in UFSAR Section 4.4.2.2.1. The methodology for this change is the same as that previously approved by the NRC. The penalty reduces the margin to the applicable safety analysis limits and so is conservative. |
| | The evaluation determined that prior NRC approval was not required.}} |
|
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Category:Annual Operating Report
MONTHYEARML22116A2332022-04-26026 April 2022 Annual Environmental Operating Report ML21116A4142021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-19003627, 10 CFR 50.46 Annual Report of ECCS Model Revisions2019-03-0404 March 2019 10 CFR 50.46 Annual Report of ECCS Model Revisions NOC-AE-18003572, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report2018-05-0707 May 2018 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes and Annual Report NOC-AE-17003520, 10CFR50.59 Summary Report of Changes, Tests and Experiment from October 2015 Through September 20172017-09-25025 September 2017 10CFR50.59 Summary Report of Changes, Tests and Experiment from October 2015 Through September 2017 NOC-AE-14003180, Annual Update to the License Renewal Application (TAC Nos. ME4936 and ME4937)2014-10-22022 October 2014 Annual Update to the License Renewal Application (TAC Nos. ME4936 and ME4937) NOC-AE-14003120, CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Model Revisions2014-04-15015 April 2014 CFR 50.46 Annual Report of Emergency Core Cooling System (ECCS) Model Revisions NOC-AE-13003042, Submittal of Report Summary 10CFR50.59 Evaluations of Changes, Tests, and Experiments Conducted2013-10-10010 October 2013 Submittal of Report Summary 10CFR50.59 Evaluations of Changes, Tests, and Experiments Conducted ML11124A1212011-04-28028 April 2011 Project, Units 1 & 2, Transmittal of 2010 Radioactive Effluent Release Report NOC-AE-10002550, Annual Environmental and Annual Radiological Environmental Operating Reports2010-04-24024 April 2010 Annual Environmental and Annual Radiological Environmental Operating Reports NOC-AE-07002196, CFR50.46 Annual Report of ECCS Model Revisions2007-09-0404 September 2007 CFR50.46 Annual Report of ECCS Model Revisions NOC-AE-07002144, CFR50.59 Summary Report2007-04-16016 April 2007 CFR50.59 Summary Report NOC-AE-05001881, 2004 Annual Environmental and Annual Radiological Environmental Operating Reports2005-04-28028 April 2005 2004 Annual Environmental and Annual Radiological Environmental Operating Reports NOC-AE-04001760, Resubmittal of the Annual Environmental Operating Report for 20032004-07-28028 July 2004 Resubmittal of the Annual Environmental Operating Report for 2003 NOC-AE-04001734, Commitment Change Summary Report2004-07-27027 July 2004 Commitment Change Summary Report NOC-AE-04001719, 2003 Annual Environmental and Annual Radiological Environmental Operating Reports2004-04-29029 April 2004 2003 Annual Environmental and Annual Radiological Environmental Operating Reports NOC-AE-03001524, Annual Environmental and Annual Radiological Environmental Operating Reports2003-04-29029 April 2003 Annual Environmental and Annual Radiological Environmental Operating Reports 2022-04-26
[Table view] Category:Letter type:NOC
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal2020-09-0808 September 2020 Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal 2023-07-11
[Table view] |
Text
Nuclear Operating Company South Texas Pro/ect Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483 September 25, 2017 NOC-AE-17003520 10CFR50.59 STI: 34543702 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 10CFR50.59 Summary Report Pursuant to the requirements of 10CFR50.59, the attached report contains a brief description and summary of the 10CFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project from October 2015 through September 2017.
There are no commitments in this letter.
If there are any questions regarding this summary report, please contact K. A. Van Daalen at (361) 972-8030 or me at (361) 972-8164.
(
Michael P. Murray Manager, Regulatory Affairs kav
Attachment:
10CFR50.59 Evaluation Summaries October 2015 - September 2017
NOC-AE-17003520 Page 2 of 2 ec:
(paper copy) (electronic copy)
Morgan, Lewis & Bockius LLP Regional Administrator, Region IV Steve Frantz, Esquire U. S. Nuclear Regulatory Commission Paul Bessette 1600 East Lamar Boulevard Arlington, TX 76011-4511 D. S. Nuclear Regulatory Comm iss io n Lisa M. Regner NRG South Texas LP Lisa M. Regner Mark Walker Senior Licensing Project Manager Jim von Suskil U.S. Nuclear Regulatory Commission Skip Zahn One White Flint North (08H04) 11555RockvillePike CPS Energy Rockville, MD 20852 Kevin Polio Cris Eugster L. D. Blaylock NRC Resident Inspector U. S. Nuclear Regulatory Commission CjtyofAustin P. 0. Box 289, Mail Code: MN116 Elaina Ball Wadsworth,TX 77483 John Wester Texas Department of State Health Services Helen Watkins Robert Free
NOC-AE-17003520 Attachment Page 1 of 3 10CFR50.59 Evaluation Summaries October 2015 - September 2017 Summaries of the following 10CFR50.59 Evaluations are provided in this attachment:
No. Condition Report Subject Number
- 1. 14-8780-308 Apply In-Situ "Normalized" Calibration Values to Main Feedwater flow Transmitters
- 2. 16-2197-15 Manual Operator Load Shed of Additional Class 1E Battery Loads during Loss of All AC Power
- 3. 14-12285-20 Modify Use ofWRB-2M DNB Correlation in UFSAR Accident Analyses
NOC-AE-17003520 Attachment Page 2 of 3 14-8780-308: Apply In-Situ "Normalized" Calibration Values to Main Feedwater flow Transmitters
Description:
The subject of this Evaluation is the application of in-situ developed correction factors to the existing main feedwater flow transmitter scaling values initially based on the venturi flow element test laboratory results.
Summary: The proposed activity involves the application of a correction factor to the existing feedwater flow transmitter scaling values initially developed based on the venturi flow element test laboratory test results and replacing these scaling values with feedwater flow transmitter scaling values corrected to match the LEFM Cameron Caldon Check Plus system measured flow. Application of these in-situ obtained scaling values represents a change in methodology as originally established for the STP 1.4% Power Uprate by application of Westinghouse WCAP-15697 and approved by the NRC for plant operation where the ultrasonic flow measurement instrumentation is out of service for greater than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> resulting in feedwater flow measured by venturi flow element based instrumentation. This evaluation shows that the results of the revised methodology are the same as, or more conservative than, the methodology being replaced.
The evaluation determined that prior NRC approval was not required.
16-2197-15: Manual Operator Load Shed of Additional Class 1 E Battery Loads during Loss of All AC Power
==
Description:==
The subject of this Evaluation is to revise the procedure for loss of all AC power as a result of a revision to Electrical Calculation 13DJ006, "125 VDC Battery Four Hour Coping Analysis."
Summary: The proposed activity involves revising STP procedure OPOP05-EO-ECOO, "Loss of All AC Power," such that an STP operator manually sheds additional Class IE battery loads during a loss of all AC power event. Currently, the subject STP procedure requires an STP operator to manually load shed ESF Load SequencerA, B and C within 30 minutes of a loss of all AC power event. In addition to this procedure step, this change involves revising the subject procedure such that STP operators also manually load shed seven additional loads and ensure five other loads remain "ON" (not load shed) on DP1201 within 30 minutes of a loss of all AC power event. This procedure change is a result of a revision to Electrical Calculation 13DJ006, "125 VDC Battery Four Hour Coping Analysis."
The evaluation determined that prior NRC approval was not required.
NOC-AE-17003520 Attachment Page 3 of 3
- 3. 14-12285-20: Modify Use ofWRB-2M DNB Correlation in UFSAR Accident Analyses
Description:
The subject of this Evaluation is to modify the use of the WRB-2M DNB Correlation in UFSAR Accident Analyses.
Summary: The change applies a conservative penalty when using the WRB-2M correlation to determine the departure from nucleate boiling (DNB) in the fuel. The penalty is applied when the fluid conditions are calculated to be in the non-conservative steam quality region of the range of applicability of the WRB-2M correlation limit described in UFSAR Section 4.4.2.2.1. The use of the penalty does not impact the WRB-2M correlation or the approved range of applicability given in UFSAR Section 4.4.2.2.1. The methodology for this change is the same as that previously approved by the NRC. The penalty reduces the margin to the applicable safety analysis limits and so is conservative.
The evaluation determined that prior NRC approval was not required.