RS-14-064, Section 5 - Summary of Regulatory Commitments

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Section 5 - Summary of Regulatory Commitments
ML14091A007
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Site: Braidwood  Constellation icon.png
Issue date: 03/31/2014
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Exelon Generation Co
To:
Office of Nuclear Reactor Regulation
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ML14091A243 List:
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RS-14-064 SL-012183, Rev. 0
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{{#Wiki_filter:5 Interim Actions Based on the screening evaluation outcome described in Section 4, the SSE exceeds the GMRS in the frequency range of 1 Hz to 10 Hz. Therefore, Braidwood station is not required to implement interim actions. However, due to high frequency exceedances, additional testing and confirmations are required. 5.1 EXPEDITED SEISMIC EVALUATION PROCESS Since the SSE exceeds the GMRS in the frequency range from 1 Hz to 10 Hz, the expedited seismic evaluation described in EPRI Report 3002000704 (Reference 4) will not be performed. 5.2 INTERIM EVALUATION OF SEISMIC HAZARD Consistent with NRC letter dated February 20, 2014, (Reference 26) the seismic hazard reevaluations presented herein are distinct from the current design and licensing bases of Braidwood station. Therefore, the results do not call into question the operability or functionality of SSCs and are not reportable pursuant to 10 CFR 50.72, "Immediate notification requirements for operating nuclear power reactors" (Reference 35), and 10 CFR 50.73, "Licensee event report system" (Reference 36). The NRC letter also requests that licensees provide an interim evaluation or actions to demonstrate that the plant can cope with the reevaluated hazard while the expedited approach and risk evaluations are conducted. In response to that request, NEI letter dated March 12, 2014 (Reference 27), provides seismic core damage risk estimates using the updated seismic hazards for the operating nuclear plants in the Central and Eastern United States. These risk estimates continue to support the following conclusions of the NRC Gl-199 Safety/Risk Assessment (Reference 28): Overall seismic core damage risk estimates are consistent with the Commission's Safety Goal Policy Statement because they are within the subsidiary objective of 104 /year for core damage frequency. The Gl-199 Safety/Risk Assessment, based in part on information from the U. S. Nuclear Regulatory Commission's (NRC's) Individual Plant Examination of External Events (IPEEE) program, indicates that no concern exists regarding adequate protection and that the current seismic design of operating reactors provides a safety margin to withstand potential earthquakes exceeding the original design basis. Braidwood station is included in the March 12, 2014 risk estimates (Reference 27). Using the methodology described in the NEI letter, all plants were shown to be below 104 /year; thus, the above conclusions apply. Braidwood Station 5-1 Report No .. SL-fJ12183 Rev5iono Correspondence No.: RSM 14-064

5.3 SEISMIC WALKDOWN INSIGHTS In response to NTTF Recommendation 2. 3, the 50.54(f) letter (Reference 1) requested licensees to perform seismic walkdowns in order to, in the context of seismic response:

1) verify that the current plant configuration is consistent with the licensing basis,
2) verify the adequacy of current strategies, monitoring, and maintenance programs, and 3) identify degraded, nonconforming, or unanalyzed conditions. Seismic walkdown guidance (EPRI 1025286, Reference 31) was developed and endorsed by the NRC as a means for all plants to provide a uniform and acceptable Industry response to NTTF 2.3 seismic walkdowns.

Seismic walkdowns in response to NTTF 2.3 for Braidwood station have been performed as documented in References 12 and 17. The seismic walkdowns for Braidwood station determined that no adverse anchorage conditions, no adverse seismic spatial interactions, and no other adverse seismic conditions existed for equipment examined during the walkdowns. Any potentially degraded, nonconforming, or unanalyzed conditions identified during the seismic walkdown program were assessed in accordance with the plant corrective action program, and were identified as being minor issues. Plant vulnerabilities identified in the Braidwood station seismic Individual Plant Examination of External Events (IPEEE) (Reference 19) were assessed as part of the seismic walkdowns (References 12 and 17). Plant improvements were identified in Sections 3 and 7 of the IPEEE (Reference 19). Table G-1 in Appendix G of the seismic walkdown reports (References 12 and 17) lists the plant improvements, the IPEEE proposed resolution, the actual resolution and resolution date. The seismic walkdown reports confirm that no open items exist as a result of the seismic portion of the IPEEE program (References 19 and 30). 5.4 BEYOND-DESIGN-BASIS SEISMIC INSIGHTS A beyond-design-basis seismic margin assessment (SMA) was performed for the seismic portion of the Braidwood station IPEEE using the EPRI SMA methodology, EPRI NP-6041-Sl (Reference 32) with the enhancements identified in NUREG-1407 (Reference 33), where applicable (Reference 19). Braidwood station is a focused scope 0.3g peak ground acceleration (PGA) plant per NUREG-1407 (Reference 33). The review level earthquake (RLE) was a median rock NUREG/CR-0098 (Reference 34) spectrum anchored to 0.3g PGA (Reference 19). The SMA determined that all items on the success path equipment list (SPEL) were found to have a seismic capacity greater than or equal to 0.30g PGA, and the plant was assigned a seismic capacity High Confidence Low Probability of Failure (HCLPF) of Q.3g PGA. No programmatic issues were Identified as a result of the SMA. No weak links were identified among buildings, distribution systems (which include piping and cable trays), or relays. Given Braidwood's design, and based on experiences with actual industrial facilities in moderate to severe earthquakes, it was concluded that Braidwood station possesses significant margin with respect to its design basis earthquake (Reference 19). Braidwood Station 5-2 Report No : SL-()12183 Revision o Correspondence No.: RS-1-4.06-4

6 Conclusions In accordance with the 50.54(1) letter (Reference 1) request for information, a seismic hazard and screening evaluation was performed for the Braidwood Nuclear Generating Station. This reevaluation followed the SPID guidance (Reference 3) in order to develop a GMRS for the site. The GMRS was developed solely for the purpose of screening for additional evaluation requirements in accordance with the SPID (Reference 3). The new GMRS represents a beyond-design-basis seismic demand and does not constitute a change in the plant design and licensing basis. The screening evaluation compariscn demonstrates that the SSE exceeds the GMRS in the frequency range of 1 Hz to 10 Hz. Therefore, a risk evaluation and a spent fuel pool evaluation will not be performed. Based on the screening requirements in the ESEP Guidance (Reference 4), Braidwood station will not perform an expedited seismic evaluation (ESEP) because the SSE exceeds the GMRS in the 1 Hz to 10 Hz frequency range. The GMRS exceeds the SSE in the frequency range beyond 10 Hz. Therefore, high frequency confirmations will be performed. The high frequency confirmations will be performed ln accordance with the schedule provided by the industry to the NRC in the April 9, 2013 letter (Reference 6), and as endorsed by the NRC (Reference 25). Br13ic!wood Station 6-1 Report No : SL-Q12183, Revision o CO~espon<1011ce No.: RS-14-064

7 References

1. NRC Letter (E. J. Leeds) to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50. 54(f) Regarcing Recommendations 2.1, 2.3, and 9.3, of the Near- Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, March 2012
2. NRC Regulations Title 10, Code of Federal Regulations, Part 50, "Domestic Licensing of Production and Utilization Facilities"
3. EPRI Technical Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SP!D) for the Resolution of Fukushima Near- Term Task Force Recommendation 2.1: Seismic, dated November, 2012
4. EPRI Technical Report 3002000704, Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, dated May 2013
5. NRC Regulations Title 10, Code of Federal Regulations, Part 100, "Reactor Site Criteria"
6. NEI Letter (A. R. Pietrangelo) to the NRC, Proposed Path Forwarc for NTTF Recommendation 2.1: Seismic Reevaluations, April9, 2013
7. EPRI Technical Report 1021097 (NUREG-2115), Centre/ and Eastern United States Seismic Source Charecterization for Nuclear Facilities, dated January 2012
8. EPRI Technical Report 3002000717, EPRI (2004, 2006) Ground-Motion Model (GMM) Review Project, dated June 2013
9. Silva, W.J., N. Abrahamson, G. Toro and C. Costantino, Description and validation of the stochastic ground motion model, Report Submitted to Brookhaven National Laboratory, Associated Universities, Inc. Upton, New York 11973, Contract No. 770573, dated 1996
10. Braidwood Station Updated Final Safety Analysis Report (UFSAR), Revision 14
11. EPRI RSM-121313-{)29, LCI Report, Braidwood Seismic Hazard and Screening Report, dated December 23, 2013
12. NRC Correspondence RS-12-159, Enclosure 1, Braidwood Generating Station Seismic Walkdown Report Unit 1, November, 2012 Bra llWood Station 7-1 Repon No.: Sl-1112183. Revision 0 Correspondence No : RSM14-o64
13. U.S. Nuclear Regulatory Commission Reg. Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants," 1973
14. Review of Existing Site Response Parameter Data for the Exelon Nuclear Fleet-Revision 1, Simpson Gumpertz & Heger Report No. 128018-R-01, dated July 17,2012, transmitted by letter from J. Clark to J. Hamel on July 18,2012
15. U. S. Nuclear Regulatory Commission Reg. Guide 1.208, "A performance-based approach to define the site-specific earthquake ground motion," 2007
16. Exelon Generation Company letter to the NRC, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2. 1 of the Near- Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, RS-13-102, dated April29, 2013
17. NRC Correspondence RS-12-159, Enclosure 2, Braidwood Generating Station Seismic Walkdown Report Unit 2, November, 2012
18. Attachment 1 to Letter from Glen T. Kaegi of Exelon to U. S. Nuclear Regulatory Commission, dated September 12, 2013 "Braidwood Station, Units 1 and 2, Descriptions of Subsurface Materials and Properties and Base Case Velocity Profiles (RS-13-205, RA-13-075, and TMI-13-104)
19. Exelon, Braidwood Nuclear Power Station Units 1 and 2, Individual Plant Examination of External Events for Severe Accident Vulnerabilities, June, 27, 1997
20. EPRI Report 1015108, Program on Technology Innovation: The Effects of High-Frequency Ground Motion on Structures, Components and Equipment in Nuclear Power Plants, June 2007
21. EPRI Report 1015109, Program on Technology Innovation: Seismic Screening of Components Sensitive to High-Frequency Vibratory Motions, October 2007
22. EPRI Report NP-7498, Industry Approach to Severe Accident Policy Implementation, November, 1991
23. EPRI Report 3002000706, High Frequency Program, Phase 1 Seismic Test Summary, September 2013
24. NRC Letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2013
25. NRC Letter, EPRI Final Draft Report XXXXXX, "Seismic Evaluation Guidance:

Augmented Approach for the Resolution of Near-Term Task Force Recommendation 2.1*. Seismic," as an Acceptable Alternative to the March 12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 Braid'NOod Station 7-2 Report No.: SL il12183. Revision o Correspondence No.: RS-14-Q64

26. NRC Letter (E. J. Leeds) to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status, Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-lchi Accident, February 20, 2014
27. NEI Letter (A. R. Pietrangelo) to the NRC, Seismic Risk Evaluations for Plants in the Central and Eastern United States, March 12, 2014
28. NUREG-0933, "A Prioritization of Generic Safety Issues;" Supplement 34, "Resolution of Generic Safety Issues;" Issue 199: Implications of Updated Probabilistic Seismic Hazard Estimates in Central and Eastern United States on Existing Plants, Revision 1, September, 2011
29. E-mail from R. Kassawaral (EPRI) to J. Clark (Exelon) dated February 27, 2014,

Subject:

Amp Tables

30. Staff Evaluation By The Office of Nuclear Reactor Regulation Related to Generic Letter 88-20, Supplement 4, Individual Plant Examination of External Events, Braidwood Nuclear Power Station, May 30, 2001
31. EPRI Technical Report 1025286, Seismic Walkdown Guidance for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, June 2012
32. EPRI NP-6041-SL, A Methodology for Assessment of Nuclear Power Plant Seismic Margin (Revision 1), dated August 1991
33. NRC NUREG-1407, Procedural and Submittal Guidance for the Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities, April1991
34. NRC NUREGICR-0098, Development of Criteria for Seismic Review of Selected Nuclear Power Plants, May 1978
35. Title 10 Code of Federal Regulations Part 50 Section 72, "Immediate notification requirements for operating nuclear power reactors"
36. Title 10 Code of Federal Regulations Part 50 Section 73, "Licensee event report system" Braidwood Station 7-3 Report No.: SL-012183. Revision 0 Correspondence No.: RS-14-o64

A Additional Tables Table A-1a: Mean and fractile seismic hazard curves for 100Hz (PGA) at Braidwood, 5% of critical damping (Reference 11) AMPS(a) . MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 7.09E-02 3.52E-02 5.12E-02 7.13E-02 9.11E-02 9.93E-02 0.001 5.15E-02 2.16E-02 3.42E-02 ' 5.05E-02 6.93E-Q2 8.23E-02 0.005 1.46E-02 5.27E-03 8.12E-03 1.32E-02 2.01E-02 3.01E-02 0.01 7.19E-03 2.22E-03 3.47E-03 6.17E-03 1.02E-02 1.64E-02 0.015 4.36E-03 1.16E-03 1.82E-03 3.52E-03 6.45E-03 1.10E-02 0.03 1.52E-03 2.88E-04 4.77E-04 1.04E-03 2.29E-03 4.77E-03 0.05 6.31E-04 9.37E-05 1.64E-04 3.84E-04 9.51E-04 2.07E-03 0.075 3.07E-04 4.01E-05 7.45E-05 1.B2E-04 4.70E-04 9.93E-04 0.1 1.83E-04 2.25E-05 4.31E-05 1.08E-04 2.84E-04 5.91E-04 0.15 8.70E-05 9.65E-06 1.98E-05 5.20E-05 1.36E-04 2.84E-04 0.3 2.26E-05 2.07E-06 4.56E-06 1.34E-05 3.68E-05 7.23E-05 0.5 7.39E-06 5.27E-07 1.29E-06 4.25E-06 1.23E-05 2.42E-05 0.75 2.76E-06 1.49E-07 4.01E-07 1.49E-06 4.70E-06 9.51E-06

1. 1.29E-06 5.27E-08 1.55E-07 6.45E-07 2.22E-06 4.63E-06 1.5 4.03E-07 1.01E-08 3.42E-08 1.69E-07 6.93E-07 1.53E-06
3. 4.09E-OB 3.79E-10 1.46E-09 1.08E-08 6.45E-08 1.74E-07
5. 5.70E-09 1.11E-10 1.64E-10 9.93E-10 B.OOE-09 2.49E-08 7.5 9.82E-1D 9.11E-11 1.11E-10 1.82E-10 1.23E-09 4.37E-09
10. 2.53E-10 8-12E-11 9.11 E-11 1.11E-10 3.37E-10 1.21E-09 Braidwood Station A-1 ReponNo: SL-ot21B3.R...,mno Carresporllence NO** RS~14'064

Table A-1b: Mean and fractile seismic hazard curves for 25 Hz at Braidwood, 5% of critical damping {Reference 11) AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 7.51 E-02 4.31E-02 5.58E-02 7.55E-02 9.37E-02 9.93E-02 0.001 5.76E-02 2.84E-02 3.95E-02 5.66E-02 7.55E-02 8.85E-02 0.005 1.95E-02 7.77E-03 1.13E-02 1.79E-02 2.68E-02 3.84E-02 0.01 1.05E-02 3.68E-03 5.42E-03 9.24E-03 1.46E-02 2.22E-02 0.015 6.82E-03 2.13E-03 3.19E-03 5.83E-03 9.93E-03 1.53E-02 0.03 2.73E-03 6.73E-04 1.04E-03 2.07E..03 4.19E-03 7.13E-03 0.05 1.21 E-03 2.49E-04 4.01E-04 8.47E-04 1.87E..03 3.52E-03 0.075 6.08E-04 1.11E-04 1.87E-04 4.07E-04 9.37E-04 1.79E-03 0.1 3.69E-04 6.36E-05 1.10E-04 2.46E-04 5.75E-04 1.08E-03 0.15 1.83E-04 3.05E-05 5.50E-05 1.25E-04 2.88E-04 5.27E-04 0.3 5.45E-05 8.72E-06 1.67E-05 3.90E-05 8.72E-05 1.51E-04 0.5 2.12E-05 3.19E-06 6.36E-06 1.55E-05 3.47E-05 5.83E-05 0.75 9.39E-06 1.31 E-06 2.68E-06 6.93E-06 1.57E-05 2.57E-05

1. 5.05E-06 6.45E-07 1.36E-06 3.68E-06 8.47E-06 1.42E-05 1.5 1.96E-06 2.13E-07 4.77E-07 1.38E-06 3.37E-06 5.75E-06
3. 3.08E-07 2.13E-08 S.SOE-08 1.90E-07 5.35E-07 1.01 E-06
5. 6.39E-08 2.68E-09 B.OOE-09 3.37E-08 1.10E-07 2.35E-07 7.5 1.61 E-08 4.63E-10 1.40E-09 6.93E-09 2.68E-08 6.54E-08
10. 5 .62E-09 1.67E-10 4.07E-10 2.04E-09 9.24E-09 2.42E-08 Table A-1c: Mean and fractile seismic hazard curves for 10Hz at Braidwood ,

5% of critical damping (Reference 11) AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 8.49E-02 5.75E..02 6.64E-02 8.47E-02 9.93E-02 9.93E-02 0.001 7.07E-02 4.19E-02 5.20E-02 7.03E-02 8.98E-02 9.93E-02 0.005 2.72E-02 1.18E-02 1.64E-02 2.57E-02 3.79E-02 4.77E-02 0.01 1.47E-02 5.75E-03 8.23E-03 1.34E-02 2.10E-02 2.76E-02 

         ~015           9.74E-03 ' 3.47E-03  5.12E-03   8.72E-03   1.42E-02   1.90E-02 0.03     4.37E-03   1.23E-03  1.90E-03   3.73E-03   6.73E-03   9.65E-03 0.05     2.17E-03 . 4.98E-04  8.12E-04   1.69E-03   3.47E-03   5.50E-03 0.075      1.16E-03  2.29E-04  3.90E-04   8.60E-U4   1.84E..03  3.14E-03 0.1     7.24E-04   1.29E-04  2.25E-04   5.12E-04   1.15E-03   2.01E-03 0.15      3.58E-04  5.66E-05  1.04E-04   2.49E-04   5.66E-04   1.01 E-03 0.3      1.01E-04  1.32E-05  2.60E-05   6.83E-05   1.67E-04   2.92E-04 0.5      3.74E-05  4.07E-06  8.60E-06   2.49E-05   6.45E-05   1.13E-04 0.75      1.62E-05  1.42E-06  3.19E-06   1.04E-05   2.84E-05   S.OSE-05
1. 8.59E-06 6.17E-07 1.49E-06 5.27E-06 1.53E-05 2.76E-05
         !      1.5      3.29E-06  1.62E-07  4.43E-07   1.87E-06   6.00E-06   1.11E-05
3. 5 .14E-07 1.08E-08 4.01E-08 2.32E-07 9.51E-07 1.92E-06
5. 1.07E..07 1.11E-09 S.OSE-09 3.73E-OB 1.95E-07 4.37E-07 7.5 2 .70E-08 2.07E-10 8.47E-10 7.03E-09 4.63E-08 1. ~8E-07
10. 9.38E-09 1.13E-10 2.60E-10 1.95E-09 1.51E-08 4 .19E-08 Braidwoltd Station A-2 Report No : Sl-012183. Revis ton 0 Correspondence No.: RS-14-{)64

Table A-1d: Mean and fractile seismic hazard curves for 5Hz at Braidwood, 5% of critical damping (Reference 11) AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 8.95E-02 6.26E-02 7.03E-02 8.98E-02 9.93E-02 9-93E-02 0.001 7.85E-02 4.90E-02 6.00E-02 7.89E-02 9.79E-02 9.93E-02 0.005 3.33E-02 1.49E-02 2.04E-02 3.19E-02 4.63E-02 5.66E-02 0.01 1.77E-02 7.34E-03 1.04E-02 1.67E-02 2.49E-02 3.14E-02 0.015 1.15E-02 4.56E-03 6.64E-03 1.08E-02 1.64E-02 2.10E-02 0.03 4.97E-03 1.69E-03 2.57E-03 4.50E-03 7.45E-03 9.79E-03 0.05 2.38E-03 6.93E-04 1.07E-03 2.01E-03 3.68E-03 5.35E-03 0.075 1.21E-03 3.14E-04 4.90E-04 9.65E-04 1.87E-03 3.01E-03 0.1 7.21 E-04 1.72E-04 2.72E-04 5.50E-04 1.10E-03 1.87E-03 0.15 3.32E-04 7.03E-05 1.16E-04 2.46E-04 5.05E-04 6.85E-04 0.3 8.19E-05 1.46E-05 2.64E-05 6.09E-05 1.32E-04 2.22E-04 0.5 2.82E-05 4.37E-06 8.47E-06 2.07E-05 4.70E-05 7.66E-05 0.75 1.16E-05 1.55E-06 3.19E-06 8.35E-06 1.95E-05 3.28E-05

1. 5.94E-06 6.93E-07 1.49E-06 4.13E-06 1.01 E-05 1.74E-05 1.5 2.17E-06 1.95E-07 4.50E-07 1.40E-06 3.79E-06 6.73E-06
3. 3.12E-07 1.34E-08 3.79E-08 1.60E-07 5.50E-07 1.11E-06
5. 6.15E-08 1.23E-09 4.07E-09 2-35E-08 1.05E-07 2.46E-07 7.5 1.50E-08 2.01 E-10 5.83E-10 4-19E-09 2.39E-08 6.45E-08
10. 5.10E-09 1.11 E-1 0 1.82E-10 1.15E-09 7.55E-09 2.29E-08 Table A-1e: Mean and fractile seismic hazard curves for 2.5 Hz at Braidwood, 5% of critical damping (Reference 11)

AMPS(tll MEAN 0.05 0.16 0.50 O.M 0.95 I 0.0005 8.30E-02 5.50E-02 6.45E-02 8.23E-02 9.93E-02 9.93E-02 0.001 6.70E-02 3.79E-02 4.77E-02 6.54E-02 8.72E-02 9.93E-02 0.005

  • 2.16E-02 9.11 E-03 r -

1.27E-02 2.01E-02 3.00E-02 3.95E-02 0.01 1.03E-02 A.07E-03_ 5.83E-03 9.51E-03 1.49E-02 1.92E-02 I 0.015 6.39E-03 2.29E-03 3.42E-03 5.91E-03 §.37E-03 1.21E-02 0.03 2.49E-03 6.64E-04 1.05E-03 2.13E-t13 3.&5E-03 5.58E-03 0.05 1.04E-03 2.16E-04 3.63E-(14 7.89E-04 1.fl§E-03 2.16E-03 

        !    0.075       4.54E-04   8.12E-(15   1.40E-04 _a 19E-04_ : 7.34_E-04     1.29E-03 i      0.1       2.37E-04   3.95E-05    6.93E-05  1.62E-04      3.79E-04    6.93E-04 I     0.15       9.10E-D5    1.38E-05   2.53E-05  6.17E-05      1.46E-04    2.68E-04 0.3       1.79E-05   2.19E-06    4.43E-06  1.20E-05      3.01E-05    5.42E-05 0.5       5.64E-06   5.35E-07    1.20E-06  3.57E-06      9.65E-06    1.77E-05 I     0.75       2.23E-06    1.60E-07   3.90E-07  1.32E-06      3.t~E-06    7.34E-06
1. 1.12E-06 6.26E-08 1.67E-07 6.17E-07 1.§5E-06 3.90E-06 1.5 4.07E-07 1.51E-06 4.50E-08 1.95E-07 7.13E-07 1.51E-06 i 3. 5.79E-08 9.51E-10 3.42E-09 2.01E-08 !I.~SE-08 2.39E-07
5. 1.10E-08 1.60E-10 4.25E-10 2.76E-09 1.S~E-08 4.77E-08 7.5 2.51E-09 1.02E-10 1.32E-10 S.OSE-10 3.~7E-09 1.13E-08
        !      10.
        -*--***-~--

8.07E-10 ~9.11E-11_ j_J_1E-10 . 1.90E-.1_Q_ ~.! .li7E-09_ 3.~_E-09 ... Braidwood Station A-3 Report No.: SL*012183, Revision 0 Correspondence No.: RS-14-()6-4

Table A-1f: Mean and fractile seismic hazard curves for 1 Hz at Braidwood, 5% of critical damping (Reference 11) AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.37E-02 2.49E-02 3.47E-02 5.27E-02 7.23E-02 8.47E-02 0.001 3.43E-02 1.38E-02 2.04E-02 3.33E-02 4.77E-02 5.83E-02 0.005 7.90E-03 2.84E-03 4.37E-03 7.34E-03 1.13E-02 1.49E-02 0.01 3.81E-03 1.05E-03 1.77E-03 3.42E-03 5.83E-03 7.89E-03 0.015 2.36E-03 4.98E-04 8.85E-04 2.01E-03 3.84E-03 5.50E-03 0.03 8.19E-04 1.05E-04 2.04E-04 5.58E-04 1.44E-03 2.42E-03 0.05 2.81E-04 2.72E-05 S.SOE-05 1.60E-04 4.77E-04 9.51E-04 0.075 1.00E-04 8.47E-06 1.74E-05 5.20E-05 1.60E-04 3.57E-04 0.1 4.47E-05 3.52E-06 7.34E-06 2.25E-05 7.13E-05 1.62E-04 0.15 1.37E-05 9.79E-07 2.16E-06 6.64E-06 2.22E-05 4.90E-05 0.3 2.02E-06 1.02E-07 2.53E-07 8.98E-07 3.42E-06 7 .66E-06 0.5 5.81E-07 1.69E-08 4.83E-08 2.16E-07 9.37E-07 2.42E-06 0.75 2.20E-07 3.57E-09 1.18E-08 6.54E-08 3.42E-07 9.65E-07

1. 1.08E-07 1.15E-09 4.07E-09 2.64E-OB 1.60E-07 4.90E-07 1.5 3.71E-08 2.57E-10 8.47E-10 6.64E-09 5.05E-08 1.72E-07
3. 4.81E-09 9.37E-11 1.18E-10 4.77E-10 4.98E-09 2.22E-08
5. 8.56E-10 8.12E-11 9.11E-11 1.27E-10 7.45E-10 3.73E-09 7.5 1.86E-10 8.12E-11 9.11 E-11 1.11E-10 1.98E-10 S.OOE-10
10. 5.79E-11 8.12E-11 9.11E-11 1.11E-10 1.20E-10 2.88E-10 Table A-1g: Mean and fractile seismic hazard curves for 0.5 Hz at Braidwood, 5% of critical damping (Reference 11)

AMPS(a) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 2.46E-02 1.13E-02 1.62E-02 2.35E-02 3.28E-02 4.07E-02 0.001 1.40E-02 6.09E-03 8.85E-03 1.31E-02 1.90E-02 2.49E-02 0.005 .. 3.43E-03 8.35E-04 1.461;-0~ 3.09E-03 5.42E-03 7.34E-03 0.01 1.69E-03 2.13E-04 4.43E-04 1.29E-03 3.01E-03 4.50E-03 0.015 9.92E-04 8.12E-05 1.87E-04 6.36E-04 1.84E-03 3.09E-03 0.03 2.92E-04 1.21 E-05 3.09E-05 1.25E-04 5.12E-04 1.15E-03 0.05 8.82E-05 2.60E-06 6.64E-06 **- 2.92E-05 1.38E-04 3.84E-04 0.075 2.87E-05 7.13E-07 1.79E-06 8.12E-06 4.07E-05 1.25E-04 0.1 1.21E-05 2.72E-07 6.93E-07 3.19E-06 1.72E-05 5.27E-05 0.15 3.39E-06 6.54E-08 1.82E-07 8.23E-07 S.OSE-06 1.44E-05 0.3 4.43E-07 4.98E-09 1.64E-08 8.72E-08 6.09E-07 2.16E-06 0.5 1.20E-07 6.54E-10 2.35E-09 1.62E-08 1.36E-07 6.36E-07 0.75 4.36E-08 1.72E-10 4.98E-10 3.90E-09 4.13E-08 2.32E-07

1. 2.08E-08 1.11E-10 2.01E-10 1.38E-09 1.67E-08 1.10E-07 1.5 6.92E-09 9.11E-11 1.11 E-10 3.19E-10 4.25E-09 3.42E-08
3. 8.36E-10 8.12E-11 9.11E-11 1.11 E-10 3.63E-10 3.47E-09
5. 1.41E-10 8.12E-11 9.11E-11 1.11E-10 1.20E-10 5.42E-10 7.5 2.93E-11 8.12E-11 9.11E-11 1.11E-10 1.11E-10 1.67E-10
10. 8.80E-12 8.12E-11
                                       ------   9.11E-11     1.11E-10-----*- 1.11E-10      1.13E-10 Brai:!wood Station                                                                                    A-4 Report No : SL {.)121 83. Revision 0 Correspondence No:. RS-14-064

Table A-2a* Amplification functions for Braidwood (Reference 11) 5% of critical damping I 100Hz Median Sigma Median Sigma Median Sigma Median Sigma ! (PGA) 25Hz 10Hz 5Hz AF ln(AF) AF ln(AF) AF ln(AF) AF ln(AF) 1.00E-02 1.20E+OO 6.92E-02 j .30E-02

  • 9.93E-01 7.57E-02 1.90E-02 1.13E+OII 1.39E-01 2.0~ 1.48E+/-OO_' 1.30E*01 4.95E-02 9.69E-01 J.?OE-02 1 O?F.Q1 6.32E-01 1.29E-01 9.99E-02 1 07F+OO 1.59E-01 8.24E-02 1.4CIE+OO 1.37E-01 9.64E-02 8.81E*01 8.01E-02 2.13E-01 5.67E-01 1.47E-01 1.85E-01 1 0.4F+ll0 1.611E-01 1.44E-01 .1.45E+OO 1.40E-01 1.94E-01 8.11E*01 8.35E-02 4.43E-01 5.23E*01 1.58E-01 3.56E-01 1.01E+OO 1.61E-01 2.65E-01 1.43E+OO 1.43E-01 I 2.92E-111 7.76E-01 R .<;~F-0? : 6 76E-01 S.OOE-01 1.64E-01 5.23E-01 9.68E*01 1.63E-01 3.64E-01 1.41 E+OO_ I 1.45E-01 I 3.91E-01 7.52E-01 8.65E-02 9.09E-01 : S.OOE-01 1.67E-01 6.90E-01 9.69E-01 1.67E-01 5.02E-01 1.39E+OO 1.47E-01

! 4.93E-01 7.34E-01 8.77E-112 1.15E+OO S.OOE-01 1.69E-01 8.61E-01 9.53E-01 1.71E-01 6.22E-111 1.38E+OO 1.48E-01 7.41 E-01 7.04E-01 9.07E-02 1.73E+OO S.OOE-01 1.75E-01 1.27E+OO 9.20E-01 1.80E-01 9.13E-01 1.35E+OO 1.50E-01 1.01E+OO 6.81E-01 9.30E-02 2.36E+OO S.OOE-01 1.77E-01 1.72E+OO 8.92E-01 1.87E-01 1.22E~ 1.32E+OO 1.52E-01 1.2BE+OO 6.63E-01 9.56E-02 3.01E+OO S.OOE-01 1.79E-01 2.17E+OO B.66E-01 1.90E-01 1.54E+OO 1.29E+OO 1.59E-01 1.55E+OO 6.48E-01 9.91E-02 3.63E+OO S.OOE-01 1.82E-01 2.61E+OO 8.44E-01 1.92E-01 1.85E+OO 1.26E+OO 1.68E-01 

                                  ;~~

Median Median Sigma Median Sigma 2.5Hz 1Hz 0.5Hz AF AF lnlAFl AF ln{AF) 2.1BE-02 125E+00 , 1.19E-01 1.27E-02 1.17E+OO 9.31E-02 8.25E-03 1.06E+OO 9.19E-02 7.05E-02 1.26E+OO 1.17E-01 3.43E-02 1.17E+OO 9.12E-02 1.96E-02 1.07E+OO 8.95E-02 1.1BE-01 1.26E+OO 1.16E-01 5.51E-02 1.17E+OO 9.07E-02 3.02E-02 1.07E+OO 8.87E-02 2.12E-01 1.27E+OO 1.15E-01 9.83E-02 1.17E+OO 9.07E-02 5.11E-02 1.07E+OO 8.79E-02 3.04E-01 1.28E+OO 1.15E-01 1.36E-01 1.18E+OO 9.13E-02 7.10E-02 1.07E+OO 8.75E-02 I 3.94E-01 1.28E+OO 1.15E-01 1.75E-01 1.16E+()0 9.23E-02 9.06E-02 1.07E+OO 8.73E-02 

. 4.86E-01 1.29E+IIO            1.17E-01     2.14E-01 1.19E+OO    9.39E-02 1.10E-01 1.07E+OO   8.72E-02 7.09E-01 1.30E+OO             1.26E-01     3:10E..01 1.20E+OO   9.79E-02 1.SBE-01 1.08E+OO   8.71E-02 9.47E-01 1.30E+OO             1.41E..01    4.12E-01 1.21E+OO    1.02E-01 2.09E-01 1.08E+OO   8.71E-02 1.19E+OO 1.30E+OO             1.56E-01     5.18E-01 1.22E+OO    1.07E-01 2.62E-01 1.08E+OO   8.77E..02
. 1.43E+OO 1.29E+OO             1.63E-01     6.19E-01 1.22~+00    118E-01  3.12E-01 1.09E+OO   8.94E-02 BralllwDod Statiln                                                                                                         A-5 Report No.: SL.0121B3. ReV!sionO Correspondence M:L: RS-14-064

Tables A-2b1 and A-2b2 are tabular versions of the typical amplification factors provided in Figures 2.3.6-1 and 2.3.6-2. Values are provided for two input motion levels at approximately 104 and 1o-s mean annual frequency of exceedance. These tables concentrate on the frequency range of 0.5 Hz to 25 Hz, with values up to 100 Hz included, with a single value at 0.1 Hz included for completeness. These factors are unverified and are provided for information only. The figures should be considered the governing information. Table A-2b1. Median AFs and sigmas for Model 1, Profile 1, for 2 PGA levels (Reference 29) M1P1K1 Rock PGA=0.194 M1P1K1 PGA=0.741 Freq. med. Freq. med. Soii_SA sigma ln(AF} Soil_SA sigma ln(AF) (Hz) AF _{_Hz)_ AF 100.0 0.156 0.804 0.086 100.0 0.491 0.663 0.095 87.1 0.156 0.786 0.087 87.1 0.492 0.643 0.095 75.9 0.157 0.755 0.087 75.9 0.493 0.609 0.096 66.1 0.158 0.697 0.087 66.1 0.496 0.549 0.096 57.5 0.160 0.603 0.088 57.5 0.500 0.459 0.097 50.1 0.163 0.511 0.089 50.1 0.507 0.382 0.099 43.7 0.169 0.448 0.092 43.7 0.519 0.330 0.104 38.0 0.175 0.421 0.093 38.0 0.536 0.315 0.108 33.1 0.182 0.414 0.102 33.1 0.553 0.312 0.111 28.8 0.197 0.447 0.111 28.8 0.580 0.332 0.123 25.1 0.215 0.486 0.120 25.1 0.626 0.361 0.138 21.9 0.232 0.549 0.155 21.9 0.681 0.419 0.152 19.1 0.248 0.593 0.176 19.1 0.725 0.459 0.175 16.6 0.252 0.629 0.160 16.6 0.767 0.512 0.179 14.5 0.268 0.699 0.176 14.5 0.796 0.563 0.190 12.6 0.315 0.845 0.200 12.6 0.874 0.643 0.234 11.0 0.370 1.015 0.156 11.0 0.996 0.758 0.233 9.5 0.380 1.093 0.149 9.5 1.119 0.900 0.175 8.3 0.351 1.094 0.168 8.3 1.138 1.002 0.149 7.2 0.338 1.123 0.163 7.2 1.096 1.039 0.169 6.3 0.352 1.244 0.169 6.3 1.081 1.098 0.176 5.5 0.379 1.404 0.168 5.5 1.118 1.198 0.181 4.8 0.400 1.516 0.154 4.8 1.160 1.302 0.177 4.2 0.398 1.555 0.133 4.2 1.229 1.407 0.166 3.6 0.390 1.562 0.135 3.6 1.262 1.493 0.149 3.2 0.340 1.447 0.139 3.2 1.201 1.516 0.146 2.8 0.299 1.340 0.134 2.8 1.063 1.449 0.140 2.4 0.253 1.227 0.102 2.4 0.927 1.349 0.121 2.1 0.215 1.149 0.091 2.1 0.778 1.251 0.109 1.8 0.184 1.099 0.093 1.8 0.653 1.180 0.104 '----1:.~ '- .IL160 _ 1.099 0.091 _ _ - 1.6 0.554 1.161 0.097 Braidwood Station A-6 Report No.: SL-012183, Revision o Correspondence No.: RS-14*064

Table A-2b1: (Continued) M1P1K1 Rock PGA=0.194 M1P1K1 PGA=0.741 Freq. med. Freq. med. Soii_SA sigma ln(AF) Soil_SA sigma ln(AF) (Hz) AF (Hz} AF 1.4 0.148 1.185 0.090 1.4 0.505 1.234 0.094 1.2 0.130 1.178 0.086 1.2 0.436 1.217 0.086 1.0 0.113 1.138 0.076 1.0 0.375 1.167 0.079 0.91 0.104 1.149 0.069 0.91 0.340 1.172 0.076 0.79 0.094 1.144 0.061 0.79 0.303 1.163 0.065 0.69 0.079 1.085 0.065 0.69 0.253 1.101 0.064 0.60 0.065 1.031 0.067 0.60 0.208 1.045 0.066 0.52 0.056 1.027 0.071 0.52 0.175 1.038 0.070 0.46 0.048 1.070 0.079 0.46 0.151 1.080 0.079 0.10 0.002 1.117 0.027 0.10 0.006 1.113 0.028 Table A-2b2. Median AFs and sigmas for Model 2, Profile 1, for 2 PGA levels (Reference 29) M2P1K1 PGA=0.194 M2P1K1 PGA=0.741 Freq. med. Freq. med. Soil_SA sigma ln(AF) Soil_SA sigma ln(AF) (Hz) AF (Hz) AF 100.0 0.166 0.857 0.073 100.0 0.586 0.791 0.075 87.1 0.167 0.838 0.073 87.1 0.588 0.769 0.075 75.9 0.168 0.805 0.073 75.9 0.592 0.731 0.075 66.1 0.169 0.744 0.073 66.1 0.5!!:18 0.661 0.075 57.5 0.171 0.646 0.073 57.5 0.609 0.559 0.074 50.1 0.176 0.551 0.073 50.1 0.628 0.473 0.074 43.7 0.184 0.487 0.073 43.7 0.662 0.421 0.075 38.0 0.191 0.460 0.077 38.0 0.692 0.406 0.081 33.1 0.201 0.457 0.089 33.1 0.732 0.413 0.096 28.8 0.221 0.502 0.084 28.8 0.814 0.466 0.093 25.1 0.243 0.548 0.109 25.1 0.901 0.520 0.117 21.9 0.262 0.621 0.147 21.9 0.972 0.598 0.156 19.1 0.278 0.665 0.181 19.1 1.022 0.647 0.191 16.6 0.273 0.680 0.134 16.6 0.993 0.664 0.141 14.5 0.298 0.778 0.158 14.5 1.078 0.763 0.165 12.6 0.365 0.978 0.167 12.6 1.316 0.96C 0.173 11.0 0.422 1.160 0.131 11.0 1.516 1.154 0.132 9.5 0.409 1.175 0.190 9.5 1.455 1.171 0.191 8.3 0.365 1.138 0.161 8.3 1.287 1.133 0.162 7.2 0.357 1.188 0.155 7.2 1.249 1.184 0.156 6.3 0.378 1.339 0.157 6.3 1.312 1.334 0.157 5.5 0.409 1.515 0.143 5 .5 1.409 1.510 0.144 4.8 0.427 1.615 0.120 4 .8 1.460 1.611 0.120 4.2 0.415 1.618 0.122 4 .2 1.410 1.614 0.122 BraidwOod Station A-7 Report No.: SL-01 2 183, Revtsbn 0 Correspondence No.* RS-14-{)64

Table A-2b2: (Continued) M2P1K1 PGA-0.194 M2P1K1 PGA=0.741 Freq. med. Freq. med. Soii_SA sigma ln(AF) Soil_SA sigma ln(AF) (Hz) AF (Hz) AF 3.6 0.393 1.577 0.134 3.6 1.330 1.573 0.133 3.2 0.335 1.424 0.140 3.2 1.126 1.422 0.139 2.8 0.292 1.311 0.132 2.8 0.980 1.310 0.132 2.4 0.247 1.199 0.103 2.4 0.824 1.199 0.102 2.1 0.211 1.127 0.090 2.1 0.701 1.127 0.089 1.8 0.181 1.082 0.094 1.8 0.599 1.083 0.094 1.6 0.158 1.087 0.090 1.6 0.519 1.087 0.089 1.4 0.147 1.174 ' 0.091 1.4 0.480 1.174 0.090 1.2 0.129 1.170 0.087 1.2 0.419 1.170 0.086 1.0 0.112 1.132 0.075 1.0 0.364 1.133 0.074 0.91 0.104 1.145 0.088 0.91 0.332 1.146 0.067 0.79 0.69 0.093 0.079 

                       . 1.141 1.082 0.080 0.065 0.79 0.69 0.298 0.249 1.142 1.084 0.059 0.084 0.60        0.065       1.029      0.087        0.60   0.205  1.032      0.067 0.52        0.056       1.025      0.070        0.52   0.173  1.027      0.070 0.46        0.048   !   1.069      O.G78        0.46   0.149  1.070      0.077 0.10        0.002       1.116      0.027     I  0.10   0.006  1.109      0.028 Braidwood Station                                                                      A£ Report No ' SL-012183, Revision 0 Correspomlence No. RS*14-064

Enclosure 2

SUMMARY

OF REGULATORY COMMITMENTS The following table identifies commitments made in this document. (Any other actions discussed in the submittal represent intended or planned actions. They are described to the NRC for the NRC's information and are not regulatory commitments.) COMMITMENT TYPE COMMITTED COMMITMENT DATE OR ONE*TIME ACTION PROGRAMMATIC "OUTAGE" (Yes/No) (Yes/No) Braidwood Station, Units 1 and 2, will perform a As determined by Yes No High Frequency Confirmation evaluation in NRC prioritization accordance with EPAI Report 1025287, Section following submittal 3.4. of all nuclear power plant Seismic Hazard Re-evaluations, but no later than December 31, 2019.}}

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