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Category:Annual Operating Report
MONTHYEARML23093A2122023-04-0303 April 2023 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2022 ML22104A0782022-04-14014 April 2022 Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G W3F1-2022-0017, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20212022-04-0707 April 2022 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2021 W3F1-2021-0019, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20202021-03-30030 March 2021 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2020 W3F1-2021-0011, Spent Fuel Storage Radioactive Effluent Release Report for 20202021-02-11011 February 2021 Spent Fuel Storage Radioactive Effluent Release Report for 2020 W3F1-2021-0008, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20192021-01-20020 January 2021 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2019 W3F1-2020-0032, Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 28, 20202020-04-30030 April 2020 Report of Facility Changes, Tests and Experiments and Commitment Changes for Two Year Period Ending April 28, 2020 ML19094B0782019-04-0303 April 2019 Entergy - Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G ML17206A0342017-07-24024 July 2017 Annual Report on Westinghouse Electric Company LLC, Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2016 W3F1-2016-0044, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20152016-06-0909 June 2016 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2015 W3F1-2015-0051, Annual Report on Westinghouse Electric Company, LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20142015-07-0202 July 2015 Annual Report on Westinghouse Electric Company, LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2014 W3F1-2014-0040, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 20132014-07-0303 July 2014 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Calendar Year 2013 W3F1-2014-0031, Submittal of Annual Radiological Effluent Release Report-20132014-04-29029 April 2014 Submittal of Annual Radiological Effluent Release Report-2013 W3F1-2014-0030, Annual Radiological Environmental Operating Report 20132014-04-28028 April 2014 Annual Radiological Environmental Operating Report 2013 CNRO-2014-00003, Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G2014-04-25025 April 2014 Entergy Nuclear Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3) and 10 CFR 72.140(d) Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G W3F1-2013-0028, Annual Radiological Environmental Operating Report - 20122013-04-30030 April 2013 Annual Radiological Environmental Operating Report - 2012 CNRO-2012-00003, Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2012-04-30030 April 2012 Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(d) Notification of Application of Approved Appendix B to 10CFR72 Subpart G W3F1-2012-0037, Submittal of Annual Radiological Effluent Release Report for the Year 20112012-04-30030 April 2012 Submittal of Annual Radiological Effluent Release Report for the Year 2011 W3F1-2012-0036, Annual Radiological Environmental Operating Report-20112012-04-30030 April 2012 Annual Radiological Environmental Operating Report-2011 W3F1-2009-0029, Submittal of Annual Report on Westinghouse Electric Co., LLC, Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Cy 20082009-06-17017 June 2009 Submittal of Annual Report on Westinghouse Electric Co., LLC, Combustion Engineering Emergency Core Cooling System Performance Evaluation Models for Cy 2008 W3F1-2009-0015, Annual Radiological Environmental Operating Report - 20082009-04-30030 April 2009 Annual Radiological Environmental Operating Report - 2008 W3F1-2009-0016, Annual Radioactive Effluent Release Report - 20082009-04-30030 April 2009 Annual Radioactive Effluent Release Report - 2008 CNRO-2009-00006, Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G2009-04-13013 April 2009 Entergy Operations, Inc., Annual Report for Quality Assurance Program Manual Changes Under 10CFR50.54(a)(3) and 10CFR72.140(e) Notification of Application of Approved Appendix B to 10CFR72 Subpart G ML0818401452008-06-30030 June 2008 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models W3F1-2008-0033, Annual Radiological Environmental Operating Report for the Period of January 1 Through December 31, 20072008-04-28028 April 2008 Annual Radiological Environmental Operating Report for the Period of January 1 Through December 31, 2007 W3F1-2007-0026, Submittal of Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models2007-05-31031 May 2007 Submittal of Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models W3F1-2007-0021, Annual Radiological Environmental Operating Report, 20062007-04-30030 April 2007 Annual Radiological Environmental Operating Report, 2006 ML0511502932005-04-20020 April 2005 (Waterford 3),Annual Radiological Environmental Operating Report - 2004 W3F1-2004-0021, Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models2004-04-0505 April 2004 Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models W3F1-2003-0085, Report of Facility Changes, Tests, and Experiments and Commitment Changes2003-11-19019 November 2003 Report of Facility Changes, Tests, and Experiments and Commitment Changes W3F1-2003-0030, Annual Environmental Operating Report - 20022003-04-25025 April 2003 Annual Environmental Operating Report - 2002 W3F1-2003-0027, Annual Radiological Environmental Operating Report2003-04-25025 April 2003 Annual Radiological Environmental Operating Report W3F1-2002-0046, Ses, Annual Radiological Environmental Operating Report2002-04-23023 April 2002 Ses, Annual Radiological Environmental Operating Report 2023-04-03
[Table view] Category:Letter
MONTHYEARIR 05000382/20230042024-09-25025 September 2024 Integrated Inspection Report 05000382/2023004, Disputed Non-Cited Violation Revised ML24255A8642024-09-0606 September 2024 Rscc Wire & Cable LLC Dba Marmon Industrial Energy & Infrastructure - Part 21 Retraction of Final Notification ML24239A3972024-08-23023 August 2024 Rssc Wire & Cable LLC Dba Marmon - Part 21 Final Notification - 57243-EN 57243 IR 05000382/20240052024-08-21021 August 2024 Updated Inspection Plan and Assessment Follow-Up Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2024005 IR 05000382/20240132024-08-20020 August 2024 Notice of Violation; NRC Inspection Report 05000382/2024013 ML24220A2642024-08-20020 August 2024 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment 05000382/LER-2024-004, Automatic Reactor Trip Due to Lightning Strike2024-08-15015 August 2024 Automatic Reactor Trip Due to Lightning Strike IR 05000382/20240022024-08-0808 August 2024 Integrated Inspection Report 05000382/2024002 ML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24213A1632024-08-0101 August 2024 2024 Waterford Notification of Biennial Problem Identification and Resolution Inspection and Request for Information ML24208A0962024-07-25025 July 2024 57243-EN 57243 - Rssc Wire & Cable LLC, Dba Marmon - Part 21 Notification ML24150A3852024-06-0404 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000382/2024011) and Request for Information ML24060A2192024-05-30030 May 2024 Authorization of Alternative to Use EN-RR-01 Concerning Proposed Alternative to Adopt Code Case N-752 ML24141A1012024-05-20020 May 2024 Amended Integrated Inspection Report 05000382/2023004 ML24137A3352024-05-16016 May 2024 Automatic Reactor Trip Due to Transformer Failure ML24128A0422024-05-0707 May 2024 License Amendment Request to Remove Obsolete License Conditions IR 05000382/20240012024-05-0606 May 2024 Integrated Inspection Report 05000382/2024001 ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML24101A3882024-04-10010 April 2024 Response to Request for Confirmation of Information by the Office of Nuclear Reactor Regulation Proposed Alternative Request EN-RR-22-001 Risk-Informed Categorization and Treatment for Repair ML24089A2262024-03-29029 March 2024 Entergy Response to Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Exams IR 05000382/20244012024-03-18018 March 2024 Material Control and Accounting Program Inspection Report 05000382/2024401 ML24075A1712024-03-15015 March 2024 Nuclear Onsite Property Damage Insurance (10 CFR 50.54(w)(3)) ML24074A3742024-03-15015 March 2024 Acknowledgement of Response to NRC Inspection Report 05000382/2023004 and Disputed Non-Cited Violation ML24074A2892024-03-14014 March 2024 Proof of Financial Protection (10 CFR 140.15) ML24032A0032024-03-0606 March 2024 – Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0053 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) IR 05000382/20230062024-02-28028 February 2024 Annual Assessment Letter for Waterford Steam Electric Station, Unit 3 Report 05000382/2023006 ML24039A1992024-02-12012 February 2024 – Integrated Inspection Report 05000382/2023004 IR 05000382/20230102024-01-31031 January 2024 Comprehensive Engineering Team Inspection Report 05000382/2023010 IR 05000382/20230032024-01-23023 January 2024 Acknowledgment of Reply to a Notice of Violation NRC Inspection Report 05000382/2023003 ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 – Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML23340A2292023-12-28028 December 2023 Withdrawal of an Amendment Request to Revise Technical Specification 3/4.3.2 to Remove Exemption from Testing Certain Relays at Power to Support Elimination of Potential Single Point Vulnerability (EPID L-2022-LLA-0169)-LTR ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1442023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23312A1832023-11-14014 November 2023 Integrated Inspection Report 05000382/2023003 and Notice of Violation ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000382/20234012023-10-0404 October 2023 Cyber Security Inspection Report 05000382/2023401 (Cover Letter Only) IR 05000382/20230052023-08-21021 August 2023 Updated Inspection Plan for Waterford Steam Electric Station, Unit 3 - (Report 05000382/2023005) IR 05000382/20233012023-08-15015 August 2023 NRC Initial Operator Licensing Examination Approval 05000382/2023301 IR 05000382/20230022023-08-0808 August 2023 Integrated Inspection Report 05000382/2023002 IR 05000382/20234022023-08-0707 August 2023 NRC Security Inspection Report 05000382/2023402 (Full Report) IR 05000382/20230402023-07-12012 July 2023 Revised 95001 Supplemental Inspection Report 05000382/2023040, Exercise of Enforcement Discretion, and Follow-Up Assessment Letter ML23191A4562023-07-10010 July 2023 Notification of Comprehensive Engineering Team Inspection (050003822023010) and Request for Information ML23158A1042023-06-0808 June 2023 Information Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000382/2023401 ML23145A2272023-06-0202 June 2023 95001 Supplemental Inspection Report 05000382/2023040, and Exercise of Enforcement Discretion ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment 2024-09-06
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Entergy Nuclear South Entergy Operations, Inc.17265 River Road Killona, LA 70057-3093 OIL Tel. 504 739 6715 Fax 504 739 6698 rmurill@entergy.com Robert J. Murillo Licensing Manager Waterford 3 W3F1-2008-0008 June 30, 2008 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Annual Report on Westinghouse Electric Company LLC Combustion Engineering Emergency Core Cooling System Performance Evaluation Models Waterford Steam Electric Station, Unit 3 (Waterford 3)Docket No. 50-382 License No. NPF-38 Dear Sir or Madam This letter transmits the 10 CFR 50.46 annual report pertaining to Emergency Core Cooling System (ECCS) Evaluation changes for Calendar Year 2007 for Waterford
- 3. The Westinghouse 1999 Evaluation Model (EM) is used in the Waterford 3 Large Break Loss-of-Coolant Accident (LBLOCA) ECCS performance analysis.
There were no error corrections to the 1999 EM in calendar year 2007'except for an editorial correction in the error message for CEFLASH-4A.
Also, there were no changes or error corrections in calendar year 2007 to the Westinghouse Supplement 2 Evaluation Model (S2M), which is the EM used in the Waterford 3 Small Break Loss-of-Coolant Accident (SBLOCA) ECCS performance analysis.
There were no model changes in Calendar Year- 2007 that had a significant impact on peak clad temperature (PCT). Attachment 1 provides a summary of the calendar year 2007 changes that were made to the 1999 EM. The changes had no or insignificant impact on peak clad temperature for Appendix K large and small break LOCAs.There are no new commitments contained in this submittal.
Please contact Robert J.Murillo at (504) 739-6715 if you have questions regarding this information.
RJM/GCS/ssf Attachment(s):
Summary of the Calendar Year 2007 changes to the Westinghouse 1999 EM for Waterford 3 ,4oOz W3F17-2008-0008 Page 2 cc: Mr. Elmo E. Collins, Jr.Regional Administrator U. S. Nuclear Regulatory Commission Region IV 612 E. Lamar Blvd., Suite 400 Arlington, TX 76011-4125 NRC Senior Resident Inspector Waterford Steam Electric Station Unit 3 P.O. Box 822 Killona, LA 70066-0751 U. S. Nuclear Regulatory Commission Attn: Mr. N. Kalyanam Mail Stop O-07D1 Washington, DC 20555-0001 Wise, Carter, Child & Caraway ATTN: J. Smith P.O. Box 651 Jackson, MS 39205 Winston & Strawn ATTN: N.S. Reynolds 1700 K Street, NW Washington, DC 20006-3817 Morgan, Lewis & Bockius LLP ATTN: T.C. Poindexter 1111 Pennsylvania Avenue, NW Washington, DC 20004 71, .;Attachment I W3FI-2008-0008 Summary of the Calendar Year 2007 Changes to the Westinghouse 1999 EM for Waterford 3
Attachment 1 to W3F1 -2008-0008 Page 1 of 2 2007 Westinghouse Evaluation Model Changes for Waterford 3" Proprietary Notations in Source and Output Modifications to the source file notation and output edit headers for the major computer codes of the 1999 EM have been made to indicate the copyright status and proprietary class in conformance with Westinghouse policy." Flow Path Enthalpy Transport Numerical Stability in CEFLASH-4A An upgrade to the flow path enthalpy transport model has been implemented as an optional process improvement to give the user additional numerical stability control other than modifying time step size." Correction of an Incorrect Error Message in CEFLASH-4A The editing logic in CEFLASH-4A, the blowdown thermal-hydraulics systems code of the 1999 EM, has been modified to prevent an incorrect error message from causing the utility script, which manages the operation of the 1999 EM, from an improper termination." Upgrade to the Auto-Axial Power Shape Option in STRIKIN-II An upgrade to the computer logic has been implemented to improve the process for matching the prescribed target ASI for the 1999 EM. The improvement more accurately achieves the target ASI over a broader range of conditions than before." Auto-Generation of the STRIKIN-II Base and Case Decks A process improvement has been implemented to automatically generate the STRIKIN-II base and case decks in a manner consistent with the fuel performance data set from the FATES3B computer code, which provides initial conditions for fuel rod stored energy and rod internal pressure." Increase the Number of Radial Regions for COMZIRC The core-wide cladding oxidation is calculated using the COMZIRC computer code.COMZIRC represents the core fuel pin census with a table of values of fuel rod power versus fraction of rods. The current version allows a maximum of only 12 radial intervals to represent the core. The purpose of this change is to increase the radial detail from 12 to 120 intervals, thus allowing enhanced control of the discretionary conservatism needed to bound the core pin census with the COMZIRC input table.
Attachment 1 to W3F1-2008-0008 Page 2 of 2" Assignment of CEFLASH-4A Regions in COMZIRC The assignment-of the CEFLASH-4A radial regions to the radial pin census in COMZIRC was previously a manual operation performed by the user. Computer logic has been implemented in COMZIRC to automatically confirm and/or provide the assignment of the CEFLASH-4A radial regions to the pin census." Implementation of Cathcart-Pawel Oxidation Model and Pre-Transient Oxidation Model The alternate oxidation model and pre-transient oxidation model are used to study various aspects of new embrittlement criteria being suggested by NRC and to provide an alternate means to address NRC questions regarding the calculation of the peak cladding oxidation percentage in applications of the 1999 EM to CE plants.The new UCI (User Control Interface) options provide for automatic activation of input vector changes and ensure consistency among the other computer codes of the 1999 EM.X Update to the Auto-Generation of the STRIKIN-II Base and Case Decks These updates are categorized as general code maintenance changes to improve the operation and flexibility of this feature of the code.