Similar Documents at Hatch |
---|
Category:Annual Operating Report
MONTHYEARNL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 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-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 NL-04-0663, Annual Radiological Environmental Operating Reports for 20032004-05-14014 May 2004 Annual Radiological Environmental Operating Reports for 2003 ML0413904802004-05-14014 May 2004 Annual Radiological Environmental Operating Report 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 2024-07-19
[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
MONTHYEARIR 05000321/20240022024-08-0808 August 2024 Edwin I Hatch Nuclear Plants, Units 1 and 2 – Integrated Inspection Report 05000321-2024002 and 05000366-2024002 NL-24-0290, Response to Request for Additional Information Related to Request for Specific Exemption2024-07-26026 July 2024 Response to Request for Additional Information Related to Request for Specific Exemption NL-24-0276, Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-07-26026 July 2024 Post-Audit Supplement to License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 ML24198A1252024-07-16016 July 2024 Edwin I Hatch Nuclear Plant Units 1 - 2 Notification of Conduct of Title 10 of the Code of Federal Regulations 50 NL-24-0260, Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R312024-07-0909 July 2024 Inservice Inspection Program Owner’S Activity Report (OAR-1) for Refueling Outage 1R31 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0239, Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-1392024-06-17017 June 2024 Response to Apparent Violation in NRC Inspection Report 05000321, 366/2024090: EA-23-139 ML24163A0532024-06-14014 June 2024 Audit Plan - Alternative Seismic Method LAR NL-24-0148, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-06-0404 June 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML24149A0492024-06-0404 June 2024 SNC Fleet - Regulatory Audit in Support of Review of the License Amendment Request to Revise TS 1.1, Use and Application Definitions, and Add New Technical Specification 5.5.21 and 5.5.17, Online Monitoring Program, NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations IR 05000321/20240902024-05-15015 May 2024 NRC Inspection Report 05000321-2024090 and 05000366-2024090, Investigation Report 2-2023-003; and Apparent Violation NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0195, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water.2024-05-0707 May 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times for Residual Heat Removal Service Water. NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 IR 05000032/20240112024-04-25025 April 2024 Notification of Edwin I. Hatch Nuclear Plant - Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 0500032/2024011 and 05000366/2024011 NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 IR 05000321/20240012024-04-22022 April 2024 Plants, Units 1 & 2 - Integrated Inspection Report 05000321/2024001 and 05000366/2024001 NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint2024-04-19019 April 2024 Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint NL-24-0115, Response to Request for Additional Information Exemption Requests for Physical.2024-04-0404 April 2024 Response to Request for Additional Information Exemption Requests for Physical. NL-24-0116, Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred.2024-03-29029 March 2024 Nuclear Property Insurance Coverage as of April 1, 2024 and Licensee Guarantees of Payment of Deferred. NL-24-0062, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-03-12012 March 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML24069A0012024-03-0909 March 2024 – Correction of Amendment No. 266 Regarding License Amendment Request Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program (TSTF-425, Revision 3) NL-24-0089, Correction of Technical Specification Omission2024-03-0909 March 2024 Correction of Technical Specification Omission ML24047A0362024-03-0404 March 2024 Response to Hatch and Vogtle FOF Dates Change Request (2025) NL-24-0061, Cycle 32 Core Operating Limits Report Version 12024-03-0101 March 2024 Cycle 32 Core Operating Limits Report Version 1 IR 05000321/20230062024-02-28028 February 2024 Annual Assessment Letter Edwin I. Hatch Nuclear Plant Units 1 and 2 - Nrc Inspection Report 05000321/2023006 and 05000366/2023006 NL-24-0067, 10 CFR 72.48(d)(2) Biennial Report2024-02-26026 February 2024 10 CFR 72.48(d)(2) Biennial Report NL-24-0051, License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components2024-02-20020 February 2024 License Amendment Request to Revise Renewed Facility Operating Licenses to Adopt an Alternative Seismic Method for Categorization of Structures, Systems, and Components NL-24-0042, Response to Request for Additional Information Exemption Requests for Physical Barriers2024-02-13013 February 2024 Response to Request for Additional Information Exemption Requests for Physical Barriers NL-24-0033, Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers2024-02-0505 February 2024 Response to Question for Withholding Information from Public Disclosure Exemption Requests for Physical Barriers IR 05000321/20230042024-01-31031 January 2024 Integrated Inspection Report 05000321/2023004 and 05000366/2023004 ML24012A0652024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) NL-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. IR 05000321/20233012024-01-17017 January 2024 NRC Operator License Examination Report 05000321/2023301 and 05000366/2023301 ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) 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 IR 05000321/20234022023-11-29029 November 2023 Security Baseline Inspection Report 05000321/2023402, 05000366/2023402, and 07200036/2023401 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 IR 05000321/20230112023-11-17017 November 2023 Biennial Problem Identification and Resolution Inspection Report 050003212023011 and 050003662023011 ML23324A4472023-11-14014 November 2023 302 Exam Approval Letter IR 05000321/20230032023-11-0202 November 2023 Integrated Inspection Report 05000321/2023003, and 05000366/2023003 IR 05000321/20234032023-10-26026 October 2023 Cyber Security Inspection Report 05000321/2023403 and 05000366/2023403 IR 05000321/20234012023-10-17017 October 2023 Security Baseline Inspection Report 05000321 2023401 and 05000366 2023401 ML23250A0472023-09-20020 September 2023 Request for Additional Information Regarding License Amendment Request to Relax Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Bolts in Technical Specifications Table 1.1-1, Modes ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report IR 05000321/20230052023-08-27027 August 2023 Updated Inspection Plan for Edwin I. Hatch Nuclear Plant, Units 1 & 2 - Report 05000321/2023005 and 05000366/2023005 2024-08-08
[Table view] |
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 Docket Nos.: 50-321 50-366 U. S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant Units 1 and 2 10 CFR 50.46 ECCS Evaluation Model SOUTHERN A COMPANY NL-14-0900 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 (ML 13357 A71 0) constitute a significant change/error requiring a 30 day report. This report is provided in the Enclosure.
The requirements of 1 0 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. 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 1 0 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 Description 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 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 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 for droplet flow above a two-phase level in the core, an earlier version of the model imposed a minimum core It has been observed that for cores with greater voiding (more steam flow), this minimum 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 E-1 Estimated Effect PCT 0 F) 0 +10 +20 -20 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} Description None affecting PCT Table 1-1c-Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Summary of Changes/Errors (2013)
- Current Changes/Errors (Reference 2, 3, 4, 5) Cumulative Total E-2 Estimated Effect PCT) N/A GE14 (Of) 10 0 50 60 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 Description 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 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 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 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 E-3 Estimated Effect (ll PCT 0 F) 0 +10 +20 -20 Enclosure to NL-14-0900 Hatch Nuclear Plant 1 0 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) Description None affecting PCT Table 1-2c -Cumulative Impact of Changes/Errors Description
- Changes/Errors Previously Reported (Reference
- 1)
- Summary of Changes/Errors (2013)
- Current Changes/Errors (Reference 2, 3, 4, 5) Cumulative Total E-4 Estimated Effect PCT) N/A GE14 (OF) 10 0 50 60 Enclosure to NL-14-0900 Hatch Nuclear Plant 1 0 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