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Category:Annual Operating Report
MONTHYEARNL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-21-0606, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20202021-07-0101 July 2021 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2020 NL-20-0630, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20192020-06-19019 June 2020 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2019 NL-20-0548, Submittal of Annual Radiological Environmental Operating Reports for 20192020-05-13013 May 2020 Submittal of Annual Radiological Environmental Operating Reports for 2019 NL-19-0650, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20182019-06-0505 June 2019 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2018 NL-18-0539, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20172018-05-14014 May 2018 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2017 NL-18-0181, ISFSI 10 CFR 72.48 (d)(2) Biennial Report2018-02-22022 February 2018 ISFSI 10 CFR 72.48 (d)(2) Biennial Report NL-17-0463, Transmittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20162017-04-20020 April 2017 Transmittal of 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2016 NL-15-0802, J.M. Farley, E.I. Hatch, Vogtle - Annual Non-Radioactive Environmental Operating Reports for 20142015-04-30030 April 2015 J.M. Farley, E.I. Hatch, Vogtle - Annual Non-Radioactive Environmental Operating Reports for 2014 NL-14-0900, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report2014-06-20020 June 2014 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report NL-13-2576, CFR50.46 ECCS Evaluation Model Annual Report for 20122013-12-23023 December 2013 CFR50.46 ECCS Evaluation Model Annual Report for 2012 NL-13-1006, Annual Radiological Environmental Operating Reports for 20122013-05-15015 May 2013 Annual Radiological Environmental Operating Reports for 2012 NL-13-0889, Annual Radioactive Effluent Release Report for 20122013-04-30030 April 2013 Annual Radioactive Effluent Release Report for 2012 NL-13-0450, ISFSI and Edwin I. Hatch, Units 1, 2 and ISFSI, Annual Radioactive Effluent Release Report2013-03-0101 March 2013 ISFSI and Edwin I. Hatch, Units 1, 2 and ISFSI, Annual Radioactive Effluent Release Report NL-12-2567, CFR 50.46 ECCS Evaluation Model Annual Report for 20112012-12-18018 December 2012 CFR 50.46 ECCS Evaluation Model Annual Report for 2011 NL-11-2402, CFR 50.46 ECCS Evaluation Model Annual Reports for 20102011-12-21021 December 2011 CFR 50.46 ECCS Evaluation Model Annual Reports for 2010 NL-11-0888, Annual Radiological Environmental Operating Reports for 20102011-05-12012 May 2011 Annual Radiological Environmental Operating Reports for 2010 NL-11-0865, Annual Non-Radiological Environmental Operating Reports for 20102011-04-30030 April 2011 Annual Non-Radiological Environmental Operating Reports for 2010 NL-10-0905, Enclosure 1 - Edwin I. Hatch, Units 1 and 2, Annual Radiological Environmental Operating Report for 20092010-05-14014 May 2010 Enclosure 1 - Edwin I. Hatch, Units 1 and 2, Annual Radiological Environmental Operating Report for 2009 ML1013905352010-05-14014 May 2010 Enclosure 1 - Edwin I. Hatch, Units 1 and 2, Annual Radiological Environmental Operating Report for 2009 NL-10-0839, Submittal of Annual Non-Radiological Environmental Operating Report for 20092010-04-28028 April 2010 Submittal of Annual Non-Radiological Environmental Operating Report for 2009 NL-09-1838, CFR 50.46 ECCS Evaluation Model Annual Reports for 20082009-12-17017 December 2009 CFR 50.46 ECCS Evaluation Model Annual Reports for 2008 NL-09-0775, Annual Radiological Environmental Operating Reports for 20082009-05-14014 May 2009 Annual Radiological Environmental Operating Reports for 2008 NL-08-1735, Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20072008-12-19019 December 2008 Plants - 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2007 NL-07-1039, Annual Radiological Environmental Operating Report for 20062007-05-14014 May 2007 Annual Radiological Environmental Operating Report for 2006 NL-07-0778, Submittal of Annual Radioactive Effluent Release Reports for 20062007-04-30030 April 2007 Submittal of Annual Radioactive Effluent Release Reports for 2006 NL-06-2513, E. I. Hatch, J. M. Farley, Vogtle, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20052006-12-14014 December 2006 E. I. Hatch, J. M. Farley, Vogtle, 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2005 NL-05-1050, and Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 20042005-06-25025 June 2005 and Vogtle Electric Generating Plant 10 CFR 50.46 ECCS Evaluation Model Annual Reports for 2004 NL-05-0761, Annual Non-Radiological Environmental Operating Reports for 20042005-04-25025 April 2005 Annual Non-Radiological Environmental Operating Reports for 2004 ML0413904802004-05-14014 May 2004 Annual Radiological Environmental Operating Report for 2003. NL-04-0663, Annual Radiological Environmental Operating Reports for 20032004-05-14014 May 2004 Annual Radiological Environmental Operating Reports for 2003 NL-04-0194, Report of Facility Changes, Tests and Experiments, Safety Evaluation Summaries2004-02-10010 February 2004 Report of Facility Changes, Tests and Experiments, Safety Evaluation Summaries NL-03-0894, Annual Non-Radiological Environmental Operating Reports for 20022003-04-28028 April 2003 Annual Non-Radiological Environmental Operating Reports for 2002 ML0213605362002-05-0707 May 2002 Edwin I Hatch Annual Radiological Environmental Operating Report for 2001 ML0212002992002-04-25025 April 2002 Annual Environmental Operating Report ML0206404502002-02-27027 February 2002 Annual Operating Report for 2001 2023-04-25
[Table view] Category:Graphics incl Charts and Tables
MONTHYEARML22236A6472022-08-31031 August 2022 Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports ML15106A3612015-04-17017 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Example Vogtle 1 and 2, Change Justification Matrix NL-15-0680, Annual Report for 2014 and Significant Change/Error Report2015-04-0808 April 2015 Annual Report for 2014 and Significant Change/Error Report ML14307B7072014-12-10010 December 2014 Supplemental Information Related to Development of Seismic Risk Evaluations for Information Request Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-T NL-14-0900, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report2014-06-20020 June 2014 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report NL-10-1021, Unit 1 & 2, Request to Implement Subsequent Edition of ASME OM Code for Class 1 Safety Relief Valves with Auxiliary Actuating Devices2010-10-29029 October 2010 Unit 1 & 2, Request to Implement Subsequent Edition of ASME OM Code for Class 1 Safety Relief Valves with Auxiliary Actuating Devices ML1008100052010-02-0202 February 2010 2009 Hatch FEMA Exercise Report Oct 14th ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0503804782004-02-19019 February 2004 E-mail from Naeem Iqbal to Various Addressees; Hatch Fire Model 2022-08-31
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. NL-23-0889, Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems2023-12-0606 December 2023 Units 1 and 2 - License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water (RHRSW) and Plant Service Water (Psw) Systems NL-23-0879, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0841, Update to Notice of Intent to Pursue Subsequent License Renewal2023-11-20020 November 2023 Update to Notice of Intent to Pursue Subsequent License Renewal NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0422, Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R272023-05-30030 May 2023 Inservice Inspection Program Owner'S Activity Report for Refueling Outage 2R27 NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0179, National Pollutant Discharge Elimination System (NPDES) Permit Renewal2023-03-13013 March 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal NL-23-0101, Cycle 28 Core Operating Limits Report Version 12023-02-23023 February 2023 Cycle 28 Core Operating Limits Report Version 1 NL-23-0003, Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 12023-01-20020 January 2023 Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1 NL-23-0069, Correction of Technical Specification Omission and Typographical Error2023-01-20020 January 2023 Correction of Technical Specification Omission and Typographical Error NL-22-0316, Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-11-30030 November 2022 Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0850, Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-11-18018 November 2022 Supplement to License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0832, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF .2022-10-27027 October 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF . NL-22-0800, Supplement to Authorized Relief Request HNP-ISI-RR-05-022022-10-27027 October 2022 Supplement to Authorized Relief Request HNP-ISI-RR-05-02 NL-22-0801, Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of .2022-10-14014 October 2022 Response to Request for Additional Information Regarding: Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of . NL-22-0757, Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-09-30030 September 2022 Units 1 & 2, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b NL-22-0687, Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 22022-08-31031 August 2022 Notice of Intent to Pursue Subsequent License Renewal for Hatch Units 1 & 2 NL-22-0406, Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes2022-08-19019 August 2022 Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical Specification Table 1.1-1, Modes NL-22-0650, Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program2022-08-19019 August 2022 Units 1 and 2 - Response to Request for Confirmation of Information Regarding License Amendment Request to Revise the NFPA 805 Fire Protection Program NL-22-0590, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten2022-08-18018 August 2022 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Exten NL-22-0672, Registration of Spent Fuel Cask Use2022-08-17017 August 2022 Registration of Spent Fuel Cask Use NL-22-0564, and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use2022-07-21021 July 2022 and Vogtle Electric Generating Plant, Registration of Spent Fuel Cask Use NL-22-0510, Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20212022-07-14014 July 2022 Plants Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2021 NL-22-0499, Registration of Spent Fuel Cask Use2022-06-27027 June 2022 Registration of Spent Fuel Cask Use NL-22-0362, Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update2022-06-0101 June 2022 Southern Nuclear Operating Company, Inc. - Foreign Ownership, Control, or Influence Five-Year Renewal Filing and NRC Facility Clearance Update NL-22-0365, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R302022-05-31031 May 2022 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 1R30 NL-22-0335, Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And.2022-05-17017 May 2022 Supplement to Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-208, Revision 0, Extension of Time to Reach Mode 2 in LCO 3.0.3 And. NL-22-0344, Annual Radiological Environmental Operating Reports for 20212022-05-10010 May 2022 Annual Radiological Environmental Operating Reports for 2021 NL-22-0315, Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days2022-05-0404 May 2022 Technical Specification 5.6.6 Post Accident Monitoring Instrumentation Report for Drywell Temperature Indicator Inoperable for Greater than 30 Days NL-22-0325, Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable2022-05-0303 May 2022 Withdrawal of Emergency License Amendment Request for Technical Specification 3.7.2 Regarding One-Time Extension of Completion Time for Plant Service Water (Psw) Pump Inoperable NL-22-0283, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf.2022-04-29029 April 2022 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - Ritstf. NL-22-0271, Changes to the Physical Security Plan2022-04-19019 April 2022 Changes to the Physical Security Plan NL-22-0240, SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations2022-03-31031 March 2022 SNC Response to Regulatory Issue Summary 2022-01: Preparation and Scheduling of Operator Licensing Examinations NL-21-0918, License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 52022-03-31031 March 2022 License Amendment Request to Revise the NFPA 805 Fire Protection Program. with Attachments 3 to 5 NL-22-0220, Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 20222022-03-28028 March 2022 Units 1 and 2 - Nuclear Property Insurance Coverage as of April 1, 2022 NL-22-0221, Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2022-03-28028 March 2022 Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) 2024-01-30
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Text
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 June 20, 2014 SOUTHERN A COMPANY Docket Nos.: 50-321 NL-14-0900 50-366 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report Ladies and Gentlemen:
In accordance with the requirements of 10 CFR 50.46(a)(3)(ii), Southern Nuclear Operating Company (SNC) is submitting the enclosed Edwin I. Hatch Nuclear Plant (HNP) Units 1 & 2 emergency core cooling system (ECCS) evaluation model significant change/error report.
On May 21, 2014 SNC received four separate notifications from its fuel vendor, General Electric Hitachi I Global Nuclear Fuel (GEH/GNF), of change/error reports which each included the estimated effect on the HNP limiting ECCS analysis fuel peak cladding temperature (PCT). GEH/GNF performed evaluations of the HNP SAFERIGESTR loss of coolant accident (LOCA) analysis of record (AOR), and concluded estimated PCT impacts of 0°F, +10°F, +20°F, and -20°F for 10 CFR 50.46 reporting purposes.
The combined notifications, along with the previously reported +1 0°F change/error from the HNP ECCS Model Annual Report for 2012 (ML13357A710) constitute a significant change/error requiring a 30 day report. This report is provided in the Enclosure. The requirements of 10 CFR 50.46(a)(3)(ii) also include an annual report by licensees of changes to, or errors in, acceptable ECCS models that affect the temperature calculation and the estimated effect of changes or errors on the limiting ECCS analysis. During the 2013 calendar year, there were no additional changes/errors to the ECCS model that impacted the AOR PCT.
U. S. Nuclear Regulatory Commission NL-14-0900 Page2 This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.
Respectfully submitted, C.({.~
C. R. Pierce Regulatory Affairs Director CRP/RMJ/Iac
Enclosure:
Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. D. R. Vineyard, Vice President- Hatch Mr. B. L. lvey, Vice President - Regulatory Affairs Mr. D. R. Madison, Vice President- Fleet Operations Mr. B. J. Adams, Vice President - Engineering Mr. G. L. Johnson, Regulatory Affairs Manager - Hatch RTYPE: CHA02.004 U.S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Hatch Mr. E. D. Morris, Senior Resident Inspector- Hatch
Edwin I. Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 and Significant Change/Error Report Enclosure Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report
Enclosure to NL-14-0900 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report Edwin 1. Hatch Nuclear Plant Unit 1 SAFERIGESTR*LOCA Analysis Model Table 1-1a- Current Changes/Errors Estimated Description Effect
(~ PCT 0 F)
A new version of SAFER04A has been released (-E4). This version resolves several accumulated observations docketed on software control tracking tools, which are reported as Evaluation Model changes for an ECCS-LOCA calculation utilizing the updated SAFER code compared to earlier versions: The following updates are reported: 1. Fix for a non-physical, low prediction of channel wall temperature for quenched nodes due to alternate heat transfer mechanisms while the quench front traverses the node; 2. Fix of a logic flaw which slowed progression of the re-wetting front as a result of quench front reaching two-phase level; 3. Fix of the boundary treatment between downcomer steam and liquid nodes; 4. Fix of input manipulation in core wide metal water reaction calculation, 0
which inadvertently replaced the smeared local peaking factor constant with the input unsmeared local peaking factor in the subsequent group calculation, causing the fraction of rods assigned to each group to be slightly different; 5. Fix of a rare occurrence wherein the code aborts when attempting to divide by zero in the pressure rate of change calculation, checking mass of the node when the core is partially empty; and 6. Removal of a discontinuity when using the dynamic gap conductance model, if the fuel rod gap is initially closed and the calculation predicts gap opening. Sensitivity calculations have demonstrated that these several items individually and collectively have insignificant effect on calculated peak cladding temperature.
A new version of SAFER04A has been released (-E4). This version resolves several accumulated observations docketed on software control tracking tools, the current item being reported as an Evaluation Model error for an ECCS-LOCA calculation utilizing earlier versions and corrected in the updated SAFER code revision. A logic error has been isolated occurring with an indication that the +10 expected system mass diverges from the calculated actual system mass. This occurs when upper plenum liquid mass and core spray flow rate is low; system mass is gradually lost due to core spray being discarded, resulting in marginally less ECCS flow credited as reaching the core.
A new version of SAFER04A has been released (-E4). This version resolves several accumulated observations docketed on software control tracking tools, the current item being reported as an Evaluation Model error for an ECCS-LOCA calculation utilizing earlier versions and corrected in the updated SAFER code revision. Due to calculation of a non-physically low ~p for droplet flow above a
+20 two-phase level in the core, an earlier version of the model imposed a minimum core ~p. It has been observed that for cores with greater voiding (more steam flow), this minimum ~P could be non-conservative, actually driving the steam flow slightly, and offering inappropriate steam cooling benefit above the core two phase level.
A new version of SAFER04A has been released (-E4). This version resolves -20 E-1
Enclosure to NL-14-0900 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report several accumulated observations docketed on software control tracking tools, the current item being reported as an Evaluation Model error for an ECCS-LOCA calculation utilizing earlier versions and corrected in the updated SAFER code revision. A counter current flow limitation (CCFL) is applied on the interface between the hot bundle and the lower plenum. The pressure head applied at that location is based on the liquid water level in the bundle. It was found, upon exercising the routine to define CCFL, the output would replace the pressure head with a value revised by that calculation, resulting in a representation of pressure head slightly different from that of the calculated water level in the bundle. The iteration scheme for CCFL has been fixed in the SAFER04A E4 model so that, consistently, the level head is applied whenever CCFL is calculated in that location.
Table 1-1b- Summary of Changes/Errors (2013}
Estimated Description Effect
(~ PCT)
None affecting PCT N/A Table 1-1c- Cumulative Impact of Changes/Errors GE14 Description
~IPCTI (Of)
- Changes/Errors Previously Reported (Reference 1) 10
- Summary of Changes/Errors (2013) 0
- Current Changes/Errors (Reference 2, 3, 4, 5) 50 Cumulative Total 60 E-2
Enclosure to NL-14-0900 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report Edwin I. Hatch Nuclear Plant Unit 2 SAFERIGESTR*LOCA Analysis Model Table 1-2a- Current Changes/Errors Estimated Description Effect (ll PCT 0 F)
A new version of SAFER04A has been released (-E4). This version resolves several accumulated observations docketed on software control tracking tools, which are reported as Evaluation Model changes for an ECCS-LOCA calculation utilizing the updated SAFER code compared to earlier versions: The following updates are reported: 1. Fix for a non-physical, low prediction of channel wall temperature for quenched nodes due to alternate heat transfer mechanisms while the quench front traverses the node; 2. Fix of a logic flaw which slowed progression of the re-wetting front as a result of quench front reaching two-phase level; 3. Fix of the boundary treatment between downcomer steam and liquid nodes; 4. Fix of input manipulation in core wide metal water reaction calculation, which inadvertently replaced the smeared local peaking factor constant with the 0 input unsmeared local peaking factor in the subsequent group calculation, causing the fraction of rods assigned to each group to be slightly different; 5. Fix of a rare occurrence wherein the code aborts when attempting to divide by zero in the pressure rate of change calculation, checking mass of the node when the core is partially empty; and 6. Removal of a discontinuity when using the dynamic gap conductance model, if the fuel rod gap is initially closed and the calculation predicts gap opening. Sensitivity calculations have demonstrated that these several items individually and collectively have insignificant effect on calculated peak cladding temperature.
A new version of SAFER04A has been released (-E4). This version resolves several accumulated observations docketed on software control tracking tools, the current item being reported as an Evaluation Model error for an ECCS-LOCA calculation utilizing earlier versions and corrected in the updated SAFER code revision. A logic error has been isolated occurring with an indication that the +10 expected system mass diverges from the calculated actual system mass. This occurs when upper plenum liquid mass and core spray flow rate is low; system mass is gradually lost due to core spray being discarded, resulting in marginally less ECCS flow credited as reaching the core.
A new version of SAFER04A has been released (-E4). This version resolves several accumulated observations docketed on software control tracking tools, the current item being reported as an Evaluation Model error for an ECCS-LOCA calculation utilizing earlier versions and corrected in the updated SAFER code revision. Due to calculation of a non-physically low l1p for droplet flow above a
+20 two-phase level in the core, an earlier version of the model imposed a minimum core l1p. It has been observed that for cores with greater voiding (more steam flow), this minimum l1p could be non-conservative, actually driving the steam flow slightly, and offering inappropriate steam cooling benefit above the core two phase level.
A new version of SAFER04A has been released (-E4). This version resolves -20 E-3
Enclosure to NL-14-0900 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report several accumulated observations docketed on software control tracking tools, the current item being reported as an Evaluation Model error for an ECCS-LOCA calculation utilizing earlier versions and corrected in the updated SAFER code revision. A counter current flow limitation (CCFL) is applied on the interface between the hot bundle and the lower plenum. The pressure head applied at that location is based on the liquid water level in the bundle. It was found, upon exercising the routine to define CCFL, the output would replace the pressure head with a value revised by that calculation, resulting in a representation of pressure head slightly different from that of the calculated water level in the bundle. The iteration scheme for CCFL has been fixed in the SAFER04A E4 model so that, consistently, the level.head is applied whenever CCFL is calculated in that location.
Table 1-2b- Summary of Changes/Errors (2013)
Estimated Description Effect
(~ PCT)
None affecting PCT N/A Table 1-2c -Cumulative Impact of Changes/Errors GE14 Description
~IPCTI (OF)
- Changes/Errors Previously Reported (Reference 1) 10
- Summary of Changes/Errors (2013) 0
- Current Changes/Errors (Reference 2, 3, 4, 5) 50 Cumulative Total 60 E-4
Enclosure to NL-14-0900 Hatch Nuclear Plant 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2013 & Significant Change/Error Report
References:
- 1. Letter from C. A. Pierce to USNRC (NL-13-2576), "Edwin I. Hatch Unclear Plant Units 1 and 2, Vogtle Electric Generating Plant Units 1 and 2, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2012," dated December 23, 2013
- 2. GEH/GNF Notification Letter 2014-01, May 21, 2014
- 3. GEH/GNF Notification Letter 2014-02, May 21, 2014
- 4. GEH/GNF Notification Letter 2014-03, May 21, 2014
- 5. GEH/GNF Notification Letter 2014-04, May 21, 2014 E-5