|
---|
Category:Report
MONTHYEARRS-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed WBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report BW240017, EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements2024-04-0303 April 2024 EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements ML24094A2702024-04-0303 April 2024 MDMP Deviation Form ML24071A1152024-03-31031 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites WBL-24-007, Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program2024-03-0505 March 2024 Technical Specification (TS) 5.7.2.15 - Explosive Gas and Storage Tank Radioactivity Monitoring Program BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) ML23346A1382024-01-0303 January 2024 Regulatory Audit Summary Related to Request to Increase the Number of Tritium Producing Burnable Absorber Rods NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML24057A3052023-12-12012 December 2023 Attachment 3: EC 640287 Rev. 000 - Past Operability Test Plan Acceptance Related to 2AF01PB-K BW230054, Attachment 2: MDMP Deviation Form2023-11-17017 November 2023 Attachment 2: MDMP Deviation Form ML23321A0452023-11-17017 November 2023 EC 639996 (Byron), Revision 1 and 640160 (Braidwood), Revision 0, Technical Evaluation for NEI 03-08 Deviation of Baffle-Former Bolts Volumetric Examinations for Byron and Braidwood ML23243B0562023-08-31031 August 2023 Supplemental Information to Application for Order Approving Indirect Transfer of Control of Licenses ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) ML23073A3982023-03-31031 March 2023 TMI-2 ISFSI Biennial Update Report for 2023 TMI-23-005, Updated Spent Fuel Management Plan2023-03-21021 March 2023 Updated Spent Fuel Management Plan CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu ML22335A4632022-12-0101 December 2022 Chronology of Significant Events in Operator Licensing Since the Three Mile Island Accident (1979) BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 WBL-22-034, Update to Fire Protection Report Figures Redacted2022-08-0101 August 2022 Update to Fire Protection Report Figures Redacted NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits RS-22-071, License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds2022-06-0707 June 2022 License Renewal Response to Commitment 10 - Evaluation of Possible PWSCC Crack Initiation and Propagation in the Steam Generator Channel Head Assembly and Tube-to-Tubesheet Welds RS-22-047, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-04-0808 April 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML22101A0792022-03-23023 March 2022 TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning TMI-22-008, 2021 Aircraft Movement Data Annual Report for TMI-12022-02-28028 February 2022 2021 Aircraft Movement Data Annual Report for TMI-1 WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report ML22105A0932021-12-16016 December 2021 Attachment 3 - RSCS Technical Support Document (Tsd) No. 21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG ML21349A1062021-12-15015 December 2021 Justification for the Deviation from MRP 2019-008, Technical Evaluation 635273 CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 RS-21-112, Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-10-22022 October 2021 Updated 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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) ML21266A4262021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) ML21244A3452021-09-20020 September 2021 Proposed Alternative IST RR 9 to the Requirements of the ASME OM Code for Test Plan Group 6 Relief Valves RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21236A2882021-08-10010 August 2021 TMI-2 Pdms SAR Update 14 & QA Plan (Rev 18 & 19) Biennial Submittal 08-10-21 CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report ML21182A2412021-06-30030 June 2021 Commitment Change Summary Report BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) 2024-05-28
[Table view] Category:Technical
MONTHYEARWBL-24-022, Cycle 5 Steam Generator Tube Inspection Report2024-05-16016 May 2024 Cycle 5 Steam Generator Tube Inspection Report BW240017, EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements2024-04-0303 April 2024 EC 640658, Revision 0 Technical Evaluation for NEI 03-08 Deviation of Control Rod Guide Tube Guide Card Wear Measurements ML24071A1152024-03-31031 March 2024 U.S. Department of Energy, Office of Legacy Management, 2023 Annual Site Inspection and Monitoring Report for Uranium Mill Tailings Radiation Control Act Title I Disposal Sites BW240007, Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations2024-02-29029 February 2024 Attachment 5: BW-MISC-062 Rev. 0 - Braidwood Station Unit 2 Diesel Driven AFW MAAP Calculations ML24057A3062024-02-24024 February 2024 Attachment 4: BW-SDP-006 Rev. 0 - Braidwood 2B AF Pump Fuel Oil Leak SOP Sensitivities ML24057A3042024-01-22022 January 2024 Attachment 2: EC 640630 Rev. 000 - Documentation of Test Results with Diluted Lube Oil from Fuel In-Leakage - 28 AF Diesel Engine Past Operability CNL-24-016, Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14)2024-01-10010 January 2024 Supplement to Application to Modify the Technical Specification Surveillance Requirement 3.9.5.1 (WBN-TS-21-14) NOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23229A4992023-08-17017 August 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) ML23192A4472023-07-31031 July 2023 Staff Assessment of Updated Seismic Hazards at TVA Sites Following the NRC Process for the Ongoing Assessment of Natural Hazards Information RS-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 WBL-23-018, Revised Pressure and Temperature Limits Report (PTLR)2023-04-10010 April 2023 Revised Pressure and Temperature Limits Report (PTLR) ML23073A3982023-03-31031 March 2023 TMI-2 ISFSI Biennial Update Report for 2023 CNL-23-002, Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Sche2023-03-20020 March 2023 Application to Revise Watts Bar Nuclear Plant Units 1 and 2 Technical Specifications to Change the Number of Tritium Producing Burnable Absorber Rods (WBN-TS-21-02) and Proposed Revision to Reactor Vessel Surveillance Capsule Removal Schedu BW220062, Pressure and Temperature Limits Report (Ptlr), Revision 92022-10-20020 October 2022 Pressure and Temperature Limits Report (Ptlr), Revision 9 NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22101A0792022-03-23023 March 2022 TMI2-EN-RPT-0001, Revision 1, Determination of the Safe Fuel Mass Limit for Decommissioning ML22105A0932021-12-16016 December 2021 Attachment 3 - RSCS Technical Support Document (Tsd) No. 21-078 Rev 00 TMI-2 Source Term Limitations and Administrative Controls to Prevent Exceeding the 1 Rem EPA PAG WBL-21-057, Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-12-16016 December 2021 Cycle 4 Mid-Cycle Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report CNL-21-018, Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance .2021-12-0909 December 2021 Application to Adopt TSTF-205-A, Revision of Channel Calibration, Channel Functional Test, and Related Definitions, and TSTF-563-A, Revise Instrument Testing Definitions to Incorporate the Surveillance . WBL-21-056, Revised Pressure and Temperature Limits Report (PTLR)2021-12-0909 December 2021 Revised Pressure and Temperature Limits Report (PTLR) BW210065, Pressure and Temperature Limits Report, Revision 82021-10-27027 October 2021 Pressure and Temperature Limits Report, Revision 8 ML21266A4262021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) 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) RS-21-093, R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2021-09-0101 September 2021 R. E. Ginna, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections ML21236A2882021-08-10010 August 2021 TMI-2 Pdms SAR Update 14 & QA Plan (Rev 18 & 19) Biennial Submittal 08-10-21 CNL-21-055, Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-07-20020 July 2021 Revision to Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report BW210047, ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval2021-06-30030 June 2021 ER-BR-330-1008, Revision 0, Snubber Program Plan for the Fourth 10-Year Interval RS-21-056, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld2021-05-12012 May 2021 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Weld ML21133A2642021-05-0505 May 2021 Supplemental Information to License Amendment Request Decommissioning Technical Specifications CNL-21-040, Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-03-23023 March 2021 Supplement to Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) ML21084A2292021-03-17017 March 2021 Notification of Amended Post-Shutdown Decommissioning Activities Report Accordance with 10 CFR 50.82(a)(7), Revision 4 CNL-21-011, Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002)2021-02-25025 February 2021 Expedited Application for Approval to Use a Growth Rate Temperature Adjustment When Implementing the Generic Letter 95-05 Analysis for the (WBN TS-391-21-002) WBL-21-006, Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report2021-02-11011 February 2021 Refueling Outage 3 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria Final Report ML21133A2652021-02-0101 February 2021 Calculation TMI2-EN-RPT-0002, Revision 0, MCNP Version 6.2 Bias Determination for Low Enrichment Uranium Using the ENDF/B-VIII.0 Cross Section Library RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping RS-20-154, Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections2020-12-16016 December 2020 Application for Revision to TS 5.5.9, Steam Generator (SG) Program for a One-Time Deferral of Steam Generator Tube Inspections CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User2020-12-16016 December 2020 10 CFR 71.95 Report for 3-60B Casks User WBL-20-066, Revised Pressure and Temperature Limits Report (PTLR)2020-12-16016 December 2020 Revised Pressure and Temperature Limits Report (PTLR) CNL-20-074, Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2020-08-28028 August 2020 Submittal of Additional Supplement to License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) ML20195B1622020-06-30030 June 2020 Attachment 11 - SG-SGMP-17-25-NP, Revision 1, Foreign Object Limits Analysis for the Byron and Braidwood Unit 2 Steam Generators June 2020 WBL-20-004, Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program2020-04-16016 April 2020 Analysis of Capsule U from Watts Bar Unit 2 Reactor Vessel Radiation Surveillance Program CNL-19-082, License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06)2019-10-10010 October 2019 License Amendment Request for Measurement Uncertainty Recapture Power Uprate (WBN-TS-19-06) ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 L-19-034, Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report2019-06-18018 June 2019 Wafts Bar Nuclear Plant, Unit 1 - Technical Specification (TS) 5.9.8 - Post Accident Monitoring System (Pams) Report L-19-026, Revised Pressure and Temperature Limits Report (PTLR)2019-04-0404 April 2019 Revised Pressure and Temperature Limits Report (PTLR) ML19039A0492019-02-0808 February 2019 Amd 1 to USAR Chapter 9 Auxiliary System NRC Additional Redactions ML18348A9792018-12-14014 December 2018 Transmittal of 10 CFR 50.59 Summary Report ML18348A9722018-12-12012 December 2018 Submittal of Analytical Evaluation in Accordance with ASME Code Section XI ML17356A2692017-12-20020 December 2017 Construction Lessons Learned Report 2024-05-16
[Table view] |
Text
Evaluation of 2002 USGS National Seismic Hazard Assessment Final Report National Seismic Hazard Mapping Project U.S. Geological Survey Introduction We have developed and tested a new set of seismic hazard and deaggregation computer programs and applied them to the 29 sites of RG 1.165. The primary code uses a Monte Carlo method to sample through a series of logic trees that vary key parameters in the hazard calculation. This master code calls the hazard calculation codes that were used to make the 2002 USGS national seismic hazard maps. The new codes provide the mean seismic hazard, curve and seismic hazard curves of selected fractiles, such as 15t, 50th, and 85th. Two other new codes we have developed for this project deaggregate the results in two forms. One code deaggregates the overall mean or median hazard curves.
The other code finds the median value in each magnitude-distance bin as specified in the procedure in RG 1.165.
In the following report, we describe the logic trees used in the new procedure and show plots of the results. The logic trees are an expansion of those used in the 2002 national seismic hazard maps. We wanted to make sure that the added logic nodes did not substantially bias the mean hazard curves derived from the Monte Carlo runs relative to the mean hazard curves derived from the more limited logic trees used for the national maps. We also wanted the logic trees to produce an estimate of the uncertainties that was larger for regions that have had little historic seismicity but may have the potential for producing significant earthquakes, such as the Gulf Coast and the upper Midwest. These requirements led to extensive testing of alternative logic trees during the course of this project.
Description of Logic Trees Figures 1-3 show the logic trees used in the final calculations. For all sources, we used a logic tree of attenuaiton relations, with weighting identical to that used in the 2002 national maps. For the New Madrid source (Fig. 1) we used logic trees on characteristic magnitude, location of pseudofaults, recurrence time, and pseudofault endpoints. The first three of these are identical to those used in the 2002 maps. The recurrence time is characterized by a log-normal distribution with a variability determined from an analysis of the observed times of past large New Madrid earthquakes (1811-12, about 1450, and 900 A.D.). The logic tree on characteristic magnitude ranges from M7.3 to M8.0, essentially encompassing the range of magnitudes determined for the largest 1811-12 event by analyses of the isoseismal data by various investigators.
The logic tree for the Charleston, South Carolina source is depicted in Figure 2. The two areal source zones are specified in the node "1886 rupture model." These are the same areal zones used in the 2002 maps. The recurrence interval is .specified as a log-
2 normal distribution, with the same variability as that determined for New Madrid. The logic tree for the characteristic magnitude is the same as that used in the 2002 maps.
The logic tree for the spatially-smoothed seismicity required the most analysis for this work. To quantify the variability of the seismicity rate from the catalog, we re-sampled the catalog for each run. Originally we had also considered magnitude variability by re-assigning the magnitudes. However, we found that this biased the hazard Iwo in areas dominated by the background source zones. Since the a-value for these zones were determined from the rates of magnitude 3.0 and above, varying the magnitudes preferentially reduced the rates, since our original catalog did not include events below magnitude 3.0. Thus the mean rate was underestimated from the re-assigned magnitudes.
We removed the magnitude re-assignment from the code. Another question arose about varying the locations of the earthquakes in the catalog, after re-sampling. We found that this tended to reduce the hazard in areas with spatial clusters of earthquakes. We .think that these clusters are real and their effects should not be diluted by varying the epicentral locations. Furthermore, the spatial smoothing tends to account for uncertainties in earthquake locations. Therefore, we, did not vary the locations in the catalog.
The logic tree included a node for varying the Mmax used for the extended margin and craton Mmax zones. This Mmax is applied to all calculations involving the historic seismicity. We decided on using +- 0.2 magnitude units for the variation in the mbMax.
We wanted a symmetrical variation so as not to introduce bias with respect to the 2002 values, but we did not want to use unrealistically large values of Mmax.
The key to the logic tree for the smooted seismicity is the node for seismicity model.
The 2002 maps use four models to capture the epistemic uncertainty. These models are:
- 1) M >=3.0 since 1924, 2) M>= 4.0 since 1860, 3) M>=5.0 since 1700, and 4) background zones. In particular, we felt that the occurrence of magnitude 5 and above earthquakes provided an important guide to where we might expect future moderate or large earthquakes. The separation of the seismicity into three models based on a minimum magnitude was designed to give the occurrence of larger events more importance in the hazard assessment. Using one model with a maximum likelihood method would treat the M4 and M5 events the same as the M3 events for the a-value estimation, although they would influence the b-value calculation. We did not vary the regional b-value of 0.95 used in the calculations, which is the same as that used in the 2002 maps (for Charlevoix area we used b of 0.76). We found that the catalog resampling provided reasonable variations in seismicity rates of moderate earthquakes, without the need for varying the regional b-value.
The 2002 maps employed adaptive weighting of the four seismicity models. This procedure was implemented so as not to lower the hazard in high seismicity areas by including the background zones. For each cell used in the seismicity-rate grid, the historic seismicity rate was compared to that of the background zone. The historic seismicity rate was determined from. the weighted average of the seismicity rates from models 1-3.
When the historic seismicity rate exceeded the background zone rate, only the historic seismicity rate was used for that cell (weights of 0.5, 0.25, 0.25 for models 1-3,
3 respectively). In that case, the background zone was not considered. When the background zone rate was higher than the historic-seismicity rate for that cell, then the background zone was included in the mean seismicity rate for that cell, such that the weights were 0.4, 0.2, 0.2, 0.2 for models 1-4, respectively. The problem with this adaptive weighting is that it slightly violates the observed total rate of M3+ earthquakes by about 11%. This adaptive weighting is also described in the documentation for the 1996 maps (Frankel et al., 1996).
It is problematic applying the adaptive weighting, scheme to the Monte Carlo simulations. We want to have a uniform procedure applied to all sites. We do not want to apply a three-model draw for some sites and a four-model draw for others. Even this approach would not be the same as that used in the national maps, since the number of models used varied with different seismicity-rate cells. We concluded that it was better to sacrifice total consistency with the national hazard map procedure in order to quantify the epistemic uncertainty in a uniform manner for all sites. The results of this decision are described in the next section.
Note that the M5 model actually consists of 0.8 wt for MS's and 0.1 wt for M3 and 0.1 Weight for M4 models. We included the other two models with low weights so that drawing the M5 model would not lower the hazard to near zero at sites at large distances from M5's but close to M3's and M4's. This point will be discussed later with respect to individual sites. Without including the M3 and M4 models, sites such as North Anna that are lacking in nearby M5+ earthquakes would have many runs with very low hazard values that, we think, bias the uncertainty distribution to very low values of hazard. Using a large smoothing distance of 150 km raises the lower fractiles generated by distinct M5 earthquakes, but still results in highly asymmetric distributions. The use of the M3 and M4 models with small weights when the M5 model is drawn reduces this asymmetry.
The remaining node of the logic tree for the smoothed seismicity is that for the mblg to moment magnitude (Mw) conversion. This conversion is used in three places. First is the conversion from mblg to Mw when the attenuation relations are evaluated, since most of them are in terms of Mw. The code integrates the hazard using a truncated Gutenberg-Richter distribution for the incremental rates using mblg, the magnitude assigned in the catalog. The second procedure that uses the Mw to mblg conversion is when mblgrnax is determined from Mwmax, since the maximum magnitudes are specified in terms of Mw.
Finally, the Mw is used to calculate fault lengths used in the randomly-oriented strikes of the finite faults used in the hazard calculation. As in the 2002 maps, this node consists of the conversion formulas from Boore and Atkinson (1987) and Johnston (1996).
Logic trees were also used for the Meers and Cheraw faults. The recurrence times and characteristic magnitudes were varied for these faults. The variability of recurrence time was the same as that used for the New Madrid source. For the Cheraw fault, there is a node with branches for the characteristic and truncated Gutenberg-Richter recurrence models, as was used for the national maps. These are given equal weights, as in the national maps.
4 Results at Selected Sites For most sites the mean seismic hazard curves derived from the Monte Carlo method are very similar to those derived from the national map model. In most cases, the probabilistic ground motions derived from the Monte Carlo mean hazard curve are within 15% of those from the mean curves used in the national seismic hazard maps, for an annual probability of I x 10 -5. For each site we used 200 runs to determine the mean, median, 15th and 85th percentile hazard curves. The hazard curves for the 200 runs were ranked at each ground motion level used in the. calculations to determine the percentile hazard curves. We found that using greater than 200 runs did not significantly change the results.
Figure 4 shows the results for 10 Hz spectral acceleration (Sa) for Three Mile Island.
This example shows very good agreement between the Monte Carlo mean curve and the mean from the national maps (Frankel et al, 2002). The median and mean curves from the Monte Carlo method are very similar in. this case. In general the distribution of uncertainty is asymmetrical on a log probability log ground motion plot. That is, the ratio of the 50th/15th ground motions at 1 x 10 -5 annual probability, for example, is much greater than .the ratio of the 85th/50"h ground motions at that probability. After some testing, we concluded that this asymmetry is largely caused by the M5+ seismicity model.
In areas lacking magnitude 5 earthquakes in the catalog, the M5 models will produce very low hazard. This trend was mitigated by the large smoothing distances of 150 km used in some of the models and in the use of the M3 and M4 models with small weights in the draw for the M5 model.
The I Hz hazard curves (Figure 5) for Three Mile Island show a larger uncertainty than the 10 Hz curves. This is largely due to the greater epistemic uncertainty in the attneuaiton relations at 1 Hz compared to 10 Hz. The use of the double-comer model of Atkinson and Boore (1995) increase the epistemic uncertainty at I Hz. The Monte Carlo mean curve is slightly lower than that of the 2002 maps. We found that this is often true for sites in areas with significant historic seismicity. Part of this is due to the inclusion of the background zone in the Monte Carlo simulation as opposed to the adaptive weighting that does not use the background zone for the national maps for cells with substantial historic seismicity. At 1 Hz, the median curve in Figure 6 is significantly below the mean curve.
Figure 6 depicts the hazard curves for the South Texas site, an area removed from significant historic seismicity where the background zone hazard dominates. In this example the mean hazard curve from the Monte Carlo method is slightly higher than that from the 2002 maps. We found that this is generally true for sites where the background zones, dominate. This is likely caused by the M3,4,5 models that had large smoothing distances and therefore, contribute to the hazard even at sites far from the epicenters.
The large uncertainty for the Texas site, compared to that at Three Mile Island, is, largely caused by the contrast between the hazard from the background zone and the
5 historic seismicity near the site. This contrast is greater for South Texas, since it is distant from clusters of historic earthquakes.
The hazard curves at Watts Bar for 10 Hz S.A. (Figure 7) show trends common to sites near seismically-active areas, in this case the eastern Tennessee seismic zone. The Monte Carlo mean is somewhat below the 2002 map mean, largely because of the inclusion of the background zone in the Monte Carlo mean. The median hazard curve is very similar to the mean hazard curve, as with Three Mile Island. The hazard curve uncertainty is again asymmetric with the larger uncertainty occurring for fractiles less than the median.
6 CEUS New Madrid LogicTree Attenudion IRupture IFaIt Length I Recirrence jQChacateristic Relction I Model IVaic*ility I Intervd I Mcgnitude Toro et d.
1997 0.25 .0 Atkinson M8.0
&Boore 1995 0.25 Pseudo Fajlt: End Points:
West 25km NE Frcnkel etcd.
[*0.50 entd f 0.6-0.2rigind 440*e~p(+.50) y 1996 L0.25 0.25 continuous Ecst [25km SW 0;25 0,2 O jcprI 2001 0.125 0.15 SomervilIe 0d.12001 0.125 Figure 1. Logic tree used for New Madrid characteristic sources.
7 CEUS Chaleston LogicTree Attenuction . 1886 Recurrence IC- craeristic Reidion I RuptureModeI Intervd IMcginitude Toro efd.
1997 0.25 Atkinson
&Boore N20E OCiented 1995 Failts in aSourceArea M 7.5 0.25 Frcnke ef d., 1996 Frcnkt 0.50 I
etd.
485*e~p(+,50) y
.1996 Zoneof Cintlnuous j 0.25 River Anordles 0.50 2001 0.125 Sorrerville et d. 2001 Figure 2. Logic tree used for Charleston, SC characteristic source.
8 CEUS Snoothed Seismidty LogicTree Attenudion 01dog IRegond ISeisridty ISmoothing IMblg->Mw Rdedion Rescrping IMcirrum I Mode I Distcoa I Oxlversion IMgnitude I Boorecnd Toro 25km Atkinson ed. (1987) 1997 p0.5L Johnston 1,996) 0,5 2002 value 38 km Bootstrcp +0.2 0.25, Re-sample 0.25 Booreand catalog (2002 value AtkInson 75~ km 70.3 (1987)
-0.2 15E0km .
0.25 0.25 Johnston (1996]
)und 0.5 Zone 0.2 0,143 *Uses 0.8 M5+, 0.1 M3+, 0.1 M4+
Figure 3. Logic tree used for spatially-smoothed seismicity.
I 9
0.1 s Sa Hazard Curves for Three Mile Island Central Measure (Siod) and Variance Measu'res '(Doled/Dashed)
Red - Mean, SD; Blue - 5, 15, 50, 85, 95 %ile 1-2. Green - Mean from Frankel et al., 2002 0
-i
-o 0
0.1 s Sa (g)
4 10 1.0 s So Hazard Curves for Three Mile Island Central Measure (Solid) and Variance Measures (Dbo'ed/Dashed)
Red - Mean, SD; Blue - 2, 16, 50, 84, 98 %ile 10-2Green - Mean from Frankel et. al., 2002 0) 1.0 s So (g)
11 0.1 s So Hazard Curves for South Texas Site 10-1 Central Measure (Sold) and Variance Measures (Doffed/Dashed)
Red - Mean, SD; Blue - 5, 15, 50, 85, 95 %ile 0-2, .Green - Mean from Frankel et al., 2002
(].) ............
0 "
,. _10-4 .. -
-* , "' -........ N
-* * . '.. . N
-, -.. . ........ N NIN 0 N ...
0.1 s So (g)
12 10-1: 0.1 s So Hazard Curves for Watts Bar Central Measure'(hd) and Variance Measures O(bofed/Dashed)
Red - Mean, SD; Blue - .5, 15, 50, 85, 95 %ile io- 2 "....**..
.. ..... Green - Mean from Frankel et al., 2002 C-,
C..
ci, C-,
aL-0.1 s So (g)
13 0.1 s Sa Hazard Curves for Braidwood Central Measure '(So l) and Variance Measures. '(otted/Dash Red - Mean, SD; Blue - 5, 15, 50, 85, 95 %ile ci~ Green - Mean from Frankel et al., 2002 C-,
C
-o C-,
uJ 0
-o 0
-o 0
0~
0.1 s S ((g)