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Category:Letter type:ET
MONTHYEARET 23-0006, CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components2023-05-17017 May 2023 CFR 50.55a Request Number CI3R-01 for the Third Containment Inservice Inspection Program Interval for Proposed Alternative Frequency to Containment Unbonded Post-Tensioning System Components ET 23-0005, 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peen2023-03-16016 March 2023 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened ET 23-0003, License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications2023-03-0101 March 2023 License Amendment Request (LAR) for Removal of the Power Range Neutron Flux Rate - High Negative Rate Trip Function from Technical Specifications ET 23-0002, Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2023-02-0707 February 2023 Supplement to License Amendment Request to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 23-0004, Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2023-01-26026 January 2023 Response to Requests for Additional Information (RAI) Regarding License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0006, Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-12-0101 December 2022 Operating Corp. - Application to Revise Technical Specifications to Adopt TSTF-577-A, Revision 1, Revised Frequencies for Steam Generator Tube Inspections ET 22-0010, License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements2022-08-0202 August 2022 License Amendment Request (LAR) for Deviation from Fire Protection Program Requirements ET 22-0012, Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-07-12012 July 2022 Supplement to License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0011, Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface2022-05-31031 May 2022 Withdrawal of 10 CFR 50.55a Request I4R-08, Relief for Extension of Follow-up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head Penetration Nozzles with Mitigated Alloy 600/82/182 Peened Surface ET 22-0005, Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2022-04-13013 April 2022 Response to Request for Additional Information Regarding License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 22-0003, CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads2022-04-0606 April 2022 CFR 50.55a Request I4R-09 for the Fourth Inservice Inspection Program Interval, Relief from Examination of Reactor Vessel Flange Threads ET 22-0002, Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head .2022-04-0404 April 2022 Operating Corp 10 CFR 50.55a Request Number I4R-08 for the Fourth Inservice Inspection Program Interval, Relief for Extension of Follow Up Examination and Visual Examination Requirements for Reactor Pressure Vessel Head . ET 22-0004, Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report2022-03-15015 March 2022 Operating Corp - Response to Request for Confirmation of Information (RCI) Regarding Steam Generator Tube Inspection Report ET 22-0001, Removal of the Table of Contents from the Technical Specifications2022-01-12012 January 2022 Removal of the Table of Contents from the Technical Specifications ET 21-0017, Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-12-22022 December 2021 Response to Request for Additional Information Regarding License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0009, Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage2021-11-0101 November 2021 Results of the Steam Generator Tube Inservice Inspection During the 24th Refueling Outage ET 21-0015, Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-20020 October 2021 Withdrawal of License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0012, Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-1912021-10-11011 October 2021 Supplement to License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 21-0004, License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating2021-09-29029 September 2021 License Amendment Request - Diesel Generator Completion Time Extension for Technical Specification 3.8.1, AC Sources - Operating ET 21-0010, License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2021-09-29029 September 2021 License Amendment Request - Revision to Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation ET 21-0005, Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-1912021-08-12012 August 2021 Operating Corp., License Amendment Request for a Risk-Informed Resolution to GSI-191 ET 20-0013, Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415)2020-10-26026 October 2020 Response to Request for Additional Information Re Application for Technical Specification Change Re Risk-Informed Justification for Relocation of Specific Surveillance Frequency Requirements to Licensee Controlled Program (TSTF-415) ET 20-0011, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2020-10-0101 October 2020 Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI ET 20-0007, License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers2020-06-0808 June 2020 License Amendment Request for Replacement of Engineered Safety Features Transformers with New Transformers That Have Active Automatic Load Tap Changers ET 20-0008, Operating Corporation Update for Full Implementation of Open Phase Detection System2020-05-20020 May 2020 Operating Corporation Update for Full Implementation of Open Phase Detection System ET 20-0004, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425)2020-04-27027 April 2020 Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled Program (TSTF-425) ET 20-0002, Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 12020-01-29029 January 2020 Response to Request for Additional Information Regarding Utilizing Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 ET 19-0021, Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-12-0909 December 2019 Errata for Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0020, Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation2019-11-13013 November 2019 Supplemental Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation ET 19-0019, Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-09-10010 September 2019 Response to Request for Additional Information Revision to Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0018, Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-08-22022 August 2019 Supplement to License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0014, lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 12019-08-15015 August 2019 lnserv1ce Inspection (ISI) Program Relief Request Number 14R-07, to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, D1v1s1on 1 ET 19-0002, License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation.2019-03-18018 March 2019 License Amendment Request to Revise Technical Specification 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation. ET 19-0008, Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption.2019-03-0505 March 2019 Response to Request for Additional Information Related to Thermal Conductivity Degradation for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption. ET 19-0003, License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange2019-02-25025 February 2019 License Amendment Request to Revise Technical Specification 3.6.3 and Surveillance Requirement 3.6.3.1 to Remove Use of a Blind Flange ET 19-0001, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 42019-01-23023 January 2019 Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4 ET 18-0032, Operating Corporation Change of Date for Full Implementation of Open Phase Detection System2018-12-0707 December 2018 Operating Corporation Change of Date for Full Implementation of Open Phase Detection System ET 18-0035, Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-12-0606 December 2018 Operating Corp., Supplemental Response to RAI for License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0029, (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection2018-10-31031 October 2018 (WCGS) - Results of the Twenty First Steam Generator Tube Inservice Inspection ET 18-0018, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-06-19019 June 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0016, Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information2018-05-29029 May 2018 Response to Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools Request for Supplemental Information ET 18-0014, Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-05-29029 May 2018 Response to Request for Additional Information Regarding the License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0013, Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld2018-05-0202 May 2018 Relief Request Number I4R-06, Request for Relief from ASME Code Case N-729-4 for Reactor Vessel Head Penetration Nozzle Weld ET 18-0011, (WCGS) - Guarantee of Payment of Deferred Premiums2018-04-30030 April 2018 (WCGS) - Guarantee of Payment of Deferred Premiums ET 18-0012, Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-04-19019 April 2018 Operating Corp., Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 18-0010, Financial Protection Levels2018-03-29029 March 2018 Financial Protection Levels ET 18-0007, Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System.2018-02-15015 February 2018 Supplement to License Amendment Request for Addition of New Technical Specification 3.7.20, Class 1E Electrical Equipment Air Conditioning (A/C) System. ET 18-0005, Withdrawal of License Amendment Request for Revision to the Emergency Plan2018-02-0505 February 2018 Withdrawal of License Amendment Request for Revision to the Emergency Plan ET 18-0004, Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term2018-01-29029 January 2018 Supplement to License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analysis Including Adoption of Alternative Source Term ET 17-0025, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term2017-11-14014 November 2017 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications to Transition to Westinghouse Core Design and Safety Analyses Including Adoption of Alternative Source Term 2023-05-17
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W*o F CREEK NUCLEAR OPERATING CORPORATION John P. Broschak Vice President Engineering January 27, 2014 ET 14-0002 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
Reference:
- 1) Letter dated March 12, 2012, from E. J. Leeds and M. R. Johnson, USNRC, to M. W. Sunseri, WCNOC, "Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f)
Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-ichi Accident"
- 2) Letter dated February 15, 2013, from D. L. Skeen, USNRC, to J. E.
Pollock, NEI, "Endorsement of EPRI Final Draft Report 1025287,
'Seismic Evaluation Guidance"'
- 3) Electric Power Research Institute Report 1025287, "Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic"
- 4) Letter dated April 9, 2013, from A. R. Pietrangelo, NEI, to D. L. Skeen, USNRC, "Proposed Path Forward for NTTF Recommendation 2.1:
Seismic Reevaluations"
- 5) Letter dated May 7, 2013, from E. J. Leeds, USNRC, to J. E. Pollock, NEI, "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"
- 6) Letter ET 13-0029, dated September 12, :2013, from J. P. Broschak, WCNOC, to USNRC
Subject:
Docket No. 50-482: Correction to the Response to a Nuclear Regulatory Commission 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 - 1.5 Year Response for CEUS Sites Gentlemen:
This submittal provides a corrected response to a Nuclear Regulatory Commission (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-P.O. Box 411/ Burlington, KS 66839 / Phone: (620) 364-8831 An Equal Opportunity Employer M/F/HCNET
ET 14-0002 Page 2 of 3 ichi Accident. A corrected description of the Safe Shutdown Earthquake (SSE) Control Point is provided on page 1 of the attachment and updated velocity profiles are provided in Figure 1 and Table 1 in the attachment. The geotechnical profile data for Wolf Creek Generating Station (WCGS) is provided in Table 2 in the attachment. Reference 6 provided descriptions of subsurface materials and properties and base case velocity profiles pursuant to Reference 5.
This submittal replaces Reference 6 in its entirety.
On March 12, 2012, the NRC issued Reference 1 to all power reactor licensees and holders of construction permits in active or deferred status. Enclosure 1 of Reference 1 requested each addressee in the Central and Eastern United States (CEUS) to submit a written response consistent with the requested seismic hazard evaluation information (items 1 through 7) within 1.5 years. On February 15, 2013, the NRC issued Reference 2, endorsing the Reference 3 industry guidance for responding to Reference 1. Section 4 of Reference 3 identifies the detailed information to be included in the seismic hazard evaluation submittals.
On April 9, 2013, the Nuclear Energy Institute (NEI) submitted Reference 4 to the NRC, requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the Electric Power Research Institute (EPRI) (2004, 2006) ground motion attenuation model could be completed and used to develop that information.
NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 3) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 5, NRC agreed with this recommendation.
The attachment contains the requested descriptions of subsurface materials and properties and base case velocity profiles for WCGS. The information provided in the attachment to this letter is considered an interim product of seismic hazard development efforts being performed for the industry by EPRI. The complete and final seismic hazard reports for WCGS will be provided to the NRC in our seismic hazard submittals by March 31, 2014 in accordance with Reference 5.
This letter contains no commitments. If you have any questions concerning this matter, please contact me at (620) 364-4085, or Mr. Michael J. Westman at (620) 364-4009.
Sincerely, John P. Broschak JPB/rlt Attachment cc: M. L. Dapas (NRC), w/a C. F. Lyon (NRC), w/a N. F. O'Keefe (NRC), w/a Senior Resident Inspector (NRC), w/a
ET 14-0002 Page 3 of 3 STATE OF KANSAS )
SS COUNTY OF COFFEY )
John P. Broschak, of lawful age, being first duly sworn upon oath says that he is Vice President Engineering of Wolf Creek Nuclear Operating Corporation; that he has read the foregoing document and knows the contents thereof; that he has executed the same for and on behalf of said Corporation with full power and authority to do so; and that the! facts therein stated are true and correct to the best of his knowledge, information and belief.
Jo,. Broschak V'cresident Engineering SUBSCRIBED and sworn to before me this .2') day of .l n-*, J ,2014.
[2 GAYLE S:1EPH-EAF`ýD
-Nct.ry Put~ic - Statj cf Kans lzr--ý-'.E;,:-- -1. 7' Expiration Date
Attachment to ET 14-0002 Page 1 of 6 Near Term Task Force Recommendation 2.1: Seismic - 1.5 Year Response of Central and Eastern United States (CEUS) Plants On April 9, 2013, the Nuclear Energy Institute (NEI) submitted Reference 1 to the Nuclear Regulatory Commission (NRC), requesting NRC agreement to delay submittal of some of the CEUS seismic hazard evaluation information so that an update to the Electric Power Research Institute (EPRI) (2004, 2006) ground motion attenuation model could be completed and used to develop that information. NEI proposed that descriptions of subsurface materials and properties and base case velocity profiles (items 3a and 3b in Section 4 of Reference 2) be submitted to NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to NRC by March 31, 2014. In Reference 3, NRC agreed with this recommendation.
Wolf Creek Generating Station (WCGS) Subsurface Materials and Properties and Base Case Velocity Profiles The basic information used to create the site geologic profile at WCGS is shown in Table 2.
This site geologic profile was developed using information documented in Reference 5. The Safe Shutdown Earthquake (SSE) Control Point is defined to be at the surface at the top of the finished grade at an elevation of 1099.5 feet (335 meters) [Reference 5]. For dynamic properties of soft rock layers, modulus and damping curves were represented with two models.
The first model used rock curves taken from Reference 4, the second model assumed linear behavior. These dynamic property models were weighted equally.
The three base-case shear-wave velocity profiles used to model amplification at WCGS are shown in Figure 1. Profiles 1, 2, and 3 are weighted 0.4, 0.3, and 0.3, respectively.
Thicknesses, depths, and shear-wave velocities (Vs) corresponding to each profile are shown in Table 1.
Attachment to ET 14-0002 Page 2 of 6 Fiaure 1 Shear-Wave Velocities (Vs) for WCGS Vs profiles for Wolf Creek Site Vs (ft/sec) 0 1000 2000 3000 4000 5000 6000 7000 8000 9000 10000 0
200-400 600 800 1000 -Profile 1 1200 -Profile 2 1400 -Profile 3 1600 1800 2000 __
2200 !
2400 2600 2800
Attachment to ET 14-0002 Page 3 of 6 Table I Layer Thicknesses, Depths, and Velocities (Vs) for 3 Profiles Profile I Profile 2 Profile 3 Thick- Thick- Thick-nesslft) depth (ft) Vs(ft/s) ness(ft) depth (ft) Vs(ft/s) ness(ft) depth (ft) Vs(ft/s) 0 550 0 350 0 863 5.0 5.0 550 5.0 5.0 350 5.0 5.0 863 5.0 10.0 550 5.0 10.0 350 5.0 10.0 863 5.0 15.0 1450 5.0 15.0 928 5.0 15.0 2277 5.0 20.0 1450 5.0 20.0 928 5.0 20.0 2277 5.0 25.0 1450 5.0 25.0 928 5.0 25.0 2277 5.0 30.0 1450 5.0 30.0 928 5.0 30.0 2277 6.0 36.0 1450 6.0 36.0 928 6.0 36.0 2277 6.0 42.0 6200 6.0 42.0 3968 6.0 42.0 9285 6.0 48.0 6200 6.0 48.0 3968 6.0 48.0 9285 6.0 54.0 3500 6.0 54.0 2240 6.0 54.0 5495 6.0 60.0 3500 6.0 60.0 2240 6.0 60.0 5495 4.0 64.0 3500 4.0 64.0 2240 4.0 64.0 5495 6.0 70.0 6200 6.0 70.0 3968 6.0 70.0 9285 6.0 76.0 6200 6.0 76.0 3968 6.0 76.0 9285 6.0 82.0 6200 6.0 82.0 3968 6.0 82.0 9285 3.0 85.0 4000 3.0 85.0 2560 3.0 85.0 6280 18.0 103.0 4000 18.0 103.0 2560 18.0 103.0 6280 18.0 121.0 4000 18.0 121.0 2560 18.0 121.0 6280 18.0 139.0 4000 18.0 139.0 2560 18.0 139.0 6280 18.0 157.0 4000 18.0 157.0 2560 18.0 157.0 6280 18.0 175.0 4000 18.0 175.0 2560 18.0 175.0 6280 18.0 193.0 4000 18.0 193.0 2560 18.0 193.0 6280 18.0 211.0 4000 18.0 211.0 2560 18.0 211.0 6280 18.0 229.0 4000 18.0 229.0 2560 18.0 229.0 6280 18.0 247.0 4000 18.0 247.0 2560 18.0 247.0 6280 12.0 259.0 4000 12.0 259.0 2560 12.0 259.0 6280 1.0 260.0 8000 1.0 260.0 5120 1.0 260.0 9285 2.0 262.0 8000 2.0 262.0 5120 2.0 262.0 9285 5.0 267.0 4250 5.0 267.0 2720 5.0 267.0 6672 18.0 285.0 4250 18.0 285.0 2720 18.0 285.0 6672 18.0 303.0 4250 18.0 303.0 2720 18.0 303.0 6672 18.0 321.0 4250 18.0 321.0 2720 18.0 321.0 6672 18.0 339.0 4250 18.0 339.0 2720 18.0 339.0 6672
Attachment to ET 14-0002 Page 4 of 6 Profile 1 Profile 2 Profile 3 Thick- Thick- Thick-ness ft) depth (ft) Vs(ft/s) ness(ft) depth (ft) Vs(ft/s) ness(ft) depth (ft) Vs(ft/s) 18.0 357.0 4250 18.0 357.0 2720 18.0 357.0 6672 18.0 375.0 4250 18.0 375.0 2720 18.0 375.0 6672 18.0 393.0 4250 18.0 393.0 2720 18.0 393.0 6672 100.0 493.0 8000 100.0 493.0 5120 100.0 493.0 9285 100.1 593.0 8025 100.1 593.0 5136 100.1 593.0 9285 100.1 693.1 8075 100.1 693.1 5168 100.1 693.1 9285 100.1 793.2 8125 100.1 793.2 5200 100.1 793.2 9285 100.1 893.2 8175 100.1 893.2 5232 100.1 893.2 9285 100.1 993.3 8225 100.1 993.3 5264 100.1 993.3 9285 100.1 1093.4 8275 100.1 1093.4 5296 100.1 1093.4 9285 100.1 1193.4 8325 100.1 1193.4 5328 100.1 1193.4 9285 100.1 1293.5 8375 100.1 1293.5 5360 100.1 1293.5 9285 100.1 1393.6 8425 100.1 1393.6 5392 100.1 1393.6 9285 100.1 1493.6 8475 100.1 1493.6 5424 100.1 1493.6 9285 100.1 1593.7 8525 100.1 1593.7 5456 '100.1 1593.7 9285 100.1 1693.8 8575 100.1 1693.8 5488 100.1 1693.8 9285 100.1 1793.8 8625 100.1 1793.8 5520 100.1 1793.8 9285 100.1 1893.9 8675 100.1 1893.9 5552 100.1 1893.9 9285 100.1 1994.0 8725 100.1 1994.0 5584 100.1 1994.0 9285 100.1 2094.0 8775 100.1 2094.0 5616 100.1 2094.0 9285 100.1 2194.1 8825 100.1 2194.1 5648 100.1 2194.1 9285 100.1 2294.2 8875 100.1 2294.2 5680 100.1 2294.2 9285 100.1 2394.2 8925 100.1 2394.2 5712 100.1 2394.2 9285 100.1 2494.3 8975 100.1 2494.3 5744 100.1 2494.3 9285 100.1 2594.4 9025 100.1 2594.4 5776 100.1 2594.4 9285 105.5 2699.8 9075 105.5 2699.8 5808 105.5 2699.8 9285 3280.8 5980.6 9285 3280.8 5980.6 9285 3280.8 5980.6 9285
Attachment to ET 14-0002 Page 5 of 6 Table 2 Summary of Geotechnical Profile Data for Wolf Creek Generating Station (a)
Measured Average Shear Wave Unit Bulk Depth Compressional Wave Poisson's Velocity Weight Density (feet) Geologic Unit(s) Material Description Velocity (ft/sec) Ratio (ft/sec) (pcf) (pcf) 0-10 Residual soil and Silty clay and weathered 2,300 0.463- 500 99 weathered bedrock shale 0.475 600 113 10-36 Heumader Member Somewhat clayey calcareous 6,000 0.467- 1,400- 139 shale 0.471 1,500 36-48 Plattsmouth Member Dense, Fine-grained 14,000 0.378 6,200 160 1 6 6 (b) limestone with shale layers 165 3,500""'d 48-64 Heebner, Leavenworth Interbedded carbonaceous 7,000 0.333 and Snyderville Members shale, limestone, and clayey calcareous shale 64-82 Toronto Member Fossiliferous limestone with 11,700 0.305 6,200 147 165 (b) occasional thin shale layers 153 82-255 Unnamed Lawrence, Interbedded shale, siltstone 7,800 0.322 4,000 150-154 1 60 (b)
Amazonia, Ireland and and sandstone; a thin coal Robbins Members bed and limestone layer occur in the upper 25 feet; pure shale is present in the basal 60 feet 259-262 Haskell Member Dense, fine-grained 0 . 3 0 1 (b) 8 ,0 0 0 (b,c) 16 6 (b) limestone 262-393 Vinland, Tonganoxie and Interbedded siltstone, shale 4 ,2 5 0 (b,d) 148-154 159(b) 0 . 3 3 3 (b)
Weston Members and sandstone; pure shale is prese nt in the basal 30 feet 393-402 South Bend and Rock Dense limestone with shale 16,500 (b) 0 . 3 4 6 (b) 8 ,0 0 0 (b,c) 16 6 (b)
Lake Members and siltstone aDepths and descriptions based on Boring B-4.
b Indicates values obtained from Birdwell Elastic Property Logs, borings B-4, B-5 and B-11.
CShear wave velocity measured by Birdwell.
dShear wave velocity empirically computed by Birdwell.
Attachment to ET 14-0002 Page 6 of 6
References:
- 1. Letter from A. R. Pietrangelo, NEI, to D. L. Skeen, USNRC, "Proposed Path Forward for NTTF Recommendation 2.1: Seismic Reevaluations" April 9, 2013. ADAMS Accession No. ML13107B386.
- 2. Electric Power Research Institute Report 1025287, "Seismic Evaluation Guidance:
Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic." ADAMS Accession No. ML12333A170.
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