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| {{#Wiki_filter:Nuclear Operating Company South Texas Proect Electnrc Generating Station P0. Box 289 Wadsworth. | | {{#Wiki_filter:Nuclear Operating Company South Texas Proect Electnrc GeneratingStation P0. Box 289 Wadsworth. Texs 77483 lvvv"--- |
| Texs 77483 lvvv"---April 16, 2007 NOC-AE-07002144 1OCFR50.59 U. S. Nuclear Regulatory Commission Attention: | | April 16, 2007 NOC-AE-07002144 10CFR50.59 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 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. |
| Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 1OCFR50.59 Summary Report Pursuant to the requirements of 1OCFR50.59, the attached report contains a brief description and summary of the 1OCFR50.59 evaluations of changes, tests and experiments conducted at the South Texas Project.There are no commitments in this letter.If there are any questions regarding this summary report, please contact J. R. Morris at (361) 972-8652 or me at (361) 972-7136.Scott M. Head Manager, Licensing awh | | There are no commitments in this letter. |
| | If there are any questions regarding this summary report, please contact J. R. Morris at (361) 972-8652 or me at (361) 972-7136. |
| | Scott M. Head Manager, Licensing awh |
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| ==Attachment:== | | ==Attachment:== |
| | 2007 10CFR50.59 Evaluation Summaries STI:32143330 |
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| 2007 1OCFR50.59 Evaluation Summaries STI:32143330 NOC-AE-07002144 Page 2 of 2 cc: (paper copy)(electronic copy)Regional Administrator, Region IV U. S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Senior Resident Inspector U. S. Nuclear Regulatory Commission P. 0. Box 289, Mail Code: MN116 Wadsworth, TX 77483 C. M. Canady City of Austin Electric Utility Department 721 Barton Springs Road Austin, TX 78704 Richard A. Ratliff Bureau of Radiation Control Texas Department of State Health Services 1100 West 49th Street Austin, TX 78756-3189 A. H. Gutterman, Esquire Morgan, Lewis & Bockius LLP Mohan C. Thadani U. S. Nuclear Regulatory Commission Steve Winn Christine Jacobs Eddy Daniels Marty Ryan NRG South Texas LP Ed Alarcon J. J. Nesrsta R. K. Temple Kevin Pollo City Public Service Jon C. Wood Cox Smith Matthews C. Kirksey City of Austin Attachment NOC-AE-07002144 Page 1 of 3 Summaries of the following 1OCFR50.59 Evaluations are provided in this attachment:
| | NOC-AE-07002144 Page 2 of 2 cc: |
| 1.2.3.05-15364-10 04-12793-3 05-4840-4 Preheater Bypass Valve Test at Power Change to Failure Modes & Effects Analysis for Auxiliary Feedwater Change to Hot, Full-Power Feedwater Temperature Attachment NOC-AE-07002144 Page 2 of 3 10CFR50.59 Evaluation Summaries 1. Preheater Bypass Valve Test at Power
| | (paper copy) (electronic copy) |
| | Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani U. S. Nuclear Regulatory Commission Senior Resident Inspector Steve Winn U. S. Nuclear Regulatory Commission Christine Jacobs P. 0. Box 289, Mail Code: MN116 Eddy Daniels Wadsworth, TX 77483 Marty Ryan NRG South Texas LP C. M. Canady Ed Alarcon City of Austin J. J. Nesrsta Electric Utility Department R. K. Temple 721 Barton Springs Road Kevin Pollo Austin, TX 78704 City Public Service Richard A. Ratliff Jon C. Wood Bureau of Radiation Control Cox Smith Matthews Texas Department of State Health Services 1100 West 49th Street C. Kirksey Austin, TX 78756-3189 City of Austin |
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| == Description:==
| | Attachment NOC-AE-07002144 Page 1 of 3 Summaries of the following 10CFR50.59 Evaluations are provided in this attachment: |
| | : 1. 05-15364-10 Preheater Bypass Valve Test at Power |
| | : 2. 04-12793-3 Change to Failure Modes & Effects Analysis for Auxiliary Feedwater |
| | : 3. 05-4840-4 Change to Hot, Full-Power Feedwater Temperature |
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| Summary: This evaluation supports a change to the Preheater Bypass Valve Operability Test procedure, to perform testing required by Technical Specification 4.6.3.1, Containment Isolation Valves. The valve operability testing will be performed for Containment isolation valve A2FW-FV-7192, Steam Generator 2D Preheater Outside *Reactor Containment Bypass Valve. The test will stroke the valve during at-power operation.
| | Attachment NOC-AE-07002144 Page 2 of 3 10CFR50.59 Evaluation Summaries |
| All equipment impacted by the proposed test will stay within its design basis. All code requirements will be satisfied.
| | : 1. Preheater Bypass Valve Test at Power |
| In addition, the ensuing transient will not result in changing from a Condition I to a Condition II event. This test does not impact accident scenarios and the current dose analysis remains bounding.2. Change to Failure Modes & Effects Analysis for Auxiliary Feedwater
| |
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| == Description:== | | == Description:== |
| | This evaluation supports a change to the Preheater Bypass Valve Operability Test procedure, to perform testing required by Technical Specification 4.6.3.1, Containment Isolation Valves. The valve operability testing will be performed for Containment isolation valve A2FW-FV-7192, Steam Generator 2D Preheater Outside *Reactor Containment Bypass Valve. The test will stroke the valve during at-power operation. |
| | Summary: All equipment impacted by the proposed test will stay within its design basis. All code requirements will be satisfied. In addition, the ensuing transient will not result in changing from a Condition I to a Condition II event. This test does not impact accident scenarios and the current dose analysis remains bounding. |
| | : 2. Change to Failure Modes & Effects Analysis for Auxiliary Feedwater |
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| Summary: The change revises the STP UFSAR to reflect revised failure modes and effects analysis (FMEA) for the AFW system electrical components in the isolation valve cubicle (IVC). The change also revises accident analyses to credit faulted steam generator isolation using the safety-grade AFW outside containment isolation valves (OCIV) instead of the AFW regulating valves.The proposed change replaces the faulted SG isolation function from the operator closing the AFW REG valves to the operator closing the AFW OCIVs. The AFW OCIVs are qualified to "harsh" environment conditions.
| | == Description:== |
| The proposed change takes credit for the existing operator actions to isolate the faulted steam generator by closing the AFW OCIV or securing the pump. No new operator actions, procedure changes or equipment qualification will be performed. | | The change revises the STP UFSAR to reflect revised failure modes and effects analysis (FMEA) for the AFW system electrical components in the isolation valve cubicle (IVC). The change also revises accident analyses to credit faulted steam generator isolation using the safety-grade AFW outside containment isolation valves (OCIV) instead of the AFW regulating valves. |
| The required operator actions already exist in plant procedures No evaluation methodology is changed and no equipment or component needs to be requalified. | | Summary: The proposed change replaces the faulted SG isolation function from the operator closing the AFW REG valves to the operator closing the AFW OCIVs. The AFW OCIVs are qualified to "harsh" environment conditions. The proposed change takes credit for the existing operator actions to isolate the faulted steam generator by closing the AFW OCIV or securing the pump. No new operator actions, procedure changes or equipment qualification will be performed. The required operator actions already exist in plant procedures No evaluation methodology is changed and no equipment or component needs to be requalified. No changes will be made to equipment important to safety or to operator actions. The proposed UFSAR change revises analysis to reflect plant conditions and does not change plant configuration. The change does not introduce the possibility of a malfunction of an SSC important to safety with a different result because no new failure modes are introduced. This change does not impact accident scenarios and the current dose analysis remains bounding. |
| No changes will be made to equipment important to safety or to operator actions. The proposed UFSAR change revises analysis to reflect plant conditions and does not change plant configuration. | |
| The change does not introduce the possibility of a malfunction of an SSC important to safety with a different result because no new failure modes are introduced. | |
| This change does not impact accident scenarios and the current dose analysis remains bounding. | |
| Attachment NOC-AE-07002144 Page 3 of 3 3. Change to Hot, Full-Power Feedwater Temperature
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| ==
| | Attachment NOC-AE-07002144 Page 3 of 3 |
| Description:==
| | : 3. Change to Hot, Full-Power Feedwater Temperature |
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| Summary: The proposed change revises the UFSAR to reflect the observed hot full-power feedwater temperature.
| | == Description:== |
| This change revises the upper end of the hot full-power feedwater temperature range to 448 'F for all safety analyses described in the UFSAR.There is no change made to the operating parameters. | | The proposed change revises the UFSAR to reflect the observed hot full-power feedwater temperature. This change revises the upper end of the hot full-power feedwater temperature range to 448 'F for all safety analyses described in the UFSAR. |
| The results of the evaluation for higher HFP feedwater temperature show that all acceptance limits continue to be met, and the design basis limits for the fission product barriers are not exceeded.}} | | Summary: There is no change made to the operating parameters. The results of the evaluation for higher HFP feedwater temperature show that all acceptance limits continue to be met, and the design basis limits for the fission product barriers are not exceeded.}} |
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Category:Annual Operating Report
MONTHYEARML24116A2282024-04-25025 April 2024 Annual Environmental Operating Report ML22116A2332022-04-26026 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 2024-04-25
[Table view] Category:Letter type:NOC
MONTHYEARNOC-AE-240040, Application for Order Consenting to Direct Transfer of Licenses2024-07-31031 July 2024 Application for Order Consenting to Direct Transfer of Licenses NOC-AE-240040, Financial Assurance for Decommissioning - 2024 Update2024-03-28028 March 2024 Financial Assurance for Decommissioning - 2024 Update 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-230040, Update Foreign Ownership, Control, or Influence (FOCI)2023-12-0505 December 2023 Update Foreign Ownership, Control, or Influence (FOCI) 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 2024-07-31
[Table view] |
Text
Nuclear Operating Company South Texas Proect Electnrc GeneratingStation P0. Box 289 Wadsworth. Texs 77483 lvvv"---
April 16, 2007 NOC-AE-07002144 10CFR50.59 U. S. Nuclear Regulatory Commission Attention: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852 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.
There are no commitments in this letter.
If there are any questions regarding this summary report, please contact J. R. Morris at (361) 972-8652 or me at (361) 972-7136.
Scott M. Head Manager, Licensing awh
Attachment:
2007 10CFR50.59 Evaluation Summaries STI:32143330
NOC-AE-07002144 Page 2 of 2 cc:
(paper copy) (electronic copy)
Regional Administrator, Region IV A. H. Gutterman, Esquire U. S. Nuclear Regulatory Commission Morgan, Lewis & Bockius LLP 611 Ryan Plaza Drive, Suite 400 Arlington, Texas 76011-8064 Mohan C. Thadani U. S. Nuclear Regulatory Commission Senior Resident Inspector Steve Winn U. S. Nuclear Regulatory Commission Christine Jacobs P. 0. Box 289, Mail Code: MN116 Eddy Daniels Wadsworth, TX 77483 Marty Ryan NRG South Texas LP C. M. Canady Ed Alarcon City of Austin J. J. Nesrsta Electric Utility Department R. K. Temple 721 Barton Springs Road Kevin Pollo Austin, TX 78704 City Public Service Richard A. Ratliff Jon C. Wood Bureau of Radiation Control Cox Smith Matthews Texas Department of State Health Services 1100 West 49th Street C. Kirksey Austin, TX 78756-3189 City of Austin
Attachment NOC-AE-07002144 Page 1 of 3 Summaries of the following 10CFR50.59 Evaluations are provided in this attachment:
- 1. 05-15364-10 Preheater Bypass Valve Test at Power
- 2. 04-12793-3 Change to Failure Modes & Effects Analysis for Auxiliary Feedwater
- 3. 05-4840-4 Change to Hot, Full-Power Feedwater Temperature
Attachment NOC-AE-07002144 Page 2 of 3 10CFR50.59 Evaluation Summaries
- 1. Preheater Bypass Valve Test at Power
Description:
This evaluation supports a change to the Preheater Bypass Valve Operability Test procedure, to perform testing required by Technical Specification 4.6.3.1, Containment Isolation Valves. The valve operability testing will be performed for Containment isolation valve A2FW-FV-7192, Steam Generator 2D Preheater Outside *Reactor Containment Bypass Valve. The test will stroke the valve during at-power operation.
Summary: All equipment impacted by the proposed test will stay within its design basis. All code requirements will be satisfied. In addition, the ensuing transient will not result in changing from a Condition I to a Condition II event. This test does not impact accident scenarios and the current dose analysis remains bounding.
- 2. Change to Failure Modes & Effects Analysis for Auxiliary Feedwater
Description:
The change revises the STP UFSAR to reflect revised failure modes and effects analysis (FMEA) for the AFW system electrical components in the isolation valve cubicle (IVC). The change also revises accident analyses to credit faulted steam generator isolation using the safety-grade AFW outside containment isolation valves (OCIV) instead of the AFW regulating valves.
Summary: The proposed change replaces the faulted SG isolation function from the operator closing the AFW REG valves to the operator closing the AFW OCIVs. The AFW OCIVs are qualified to "harsh" environment conditions. The proposed change takes credit for the existing operator actions to isolate the faulted steam generator by closing the AFW OCIV or securing the pump. No new operator actions, procedure changes or equipment qualification will be performed. The required operator actions already exist in plant procedures No evaluation methodology is changed and no equipment or component needs to be requalified. No changes will be made to equipment important to safety or to operator actions. The proposed UFSAR change revises analysis to reflect plant conditions and does not change plant configuration. The change does not introduce the possibility of a malfunction of an SSC important to safety with a different result because no new failure modes are introduced. This change does not impact accident scenarios and the current dose analysis remains bounding.
Attachment NOC-AE-07002144 Page 3 of 3
- 3. Change to Hot, Full-Power Feedwater Temperature
Description:
The proposed change revises the UFSAR to reflect the observed hot full-power feedwater temperature. This change revises the upper end of the hot full-power feedwater temperature range to 448 'F for all safety analyses described in the UFSAR.
Summary: There is no change made to the operating parameters. The results of the evaluation for higher HFP feedwater temperature show that all acceptance limits continue to be met, and the design basis limits for the fission product barriers are not exceeded.