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{{Adams
#REDIRECT [[PLA-7416, High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima..]]
| number = ML15362A529
| issue date = 12/23/2015
| title = Susquehanna, Units 1 and 2 - High Frequency Supplement to Seismic Hazard Screening Report, Response to NRC Request for Information, Per 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuk
| author name = Rausch T S
| author affiliation = Susquehanna Nuclear, LLC, Talen Energy
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000387, 05000388
| license number =
| contact person =
| case reference number = PLA-7416
| document type = Letter
| page count = 6
| project =
| stage = Response to RAI
}}
 
=Text=
{{#Wiki_filter:Timothy S. Rausch President and Chief Nuclear Officer Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 Timothy.Rausch@talenenergy.com DEC 2 3 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION HIGH FREQUENCY SUPPLEMENT TO SEISMIC HAZARD SCREENING REPORT, RESPONSE TO NRC REQUEST FOR INFORMATION PURSUANT TO ENERGY 10 CFR 50.54 (f) 10 CFR 50.54(F) REGARDING RECOMMENDATION 2.1 OF THE NEAR-TERM TASK FORCE REVIEW OF INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT PLA-7416 Docket No. 50-387 and No. 50-388
 
==References:==
I. NRC Letter, Request for Information Pursuant to Title IO of the Code of Federal Regulations 50.54(/) Regarding Recommendations 2.I, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March I2, 20I2, ADAMS Accession Number ML12053A340. 2. NRC Letter, Electric Power Research Institute Report 3002000704, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.I: Seismic," as an Acceptable Alternative to the March I2, 20I2, Information Request for Seismic Reevaluations, dated May 7, 20 I3, ADAMS Accession Number MLJ3I06A33I. 3. NEI Letter, Final Draft ofindustly Seismic Evaluation Guidance (EPRI I025287), dated November 27, 20I2, ADAMS Accession Number MLI2333AI68 and ML12333A170. 4. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report I 025287, "Seismic Evaluation Guidance," dated February I5, 2013, ADAMS Accession Number MLI23I9A074. 5. PPL Letter (PLA-7I45), Susquehanna Steam Electric Station Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to IO CFR 50.54(/) Regarding Recommendation 2.I of the Near-Term TaskForce Review of Insights from the Fukushima Dai-ichi Accident, dated March 26, 20I4, ADAMS Accession Number MLI4085A398. 6. NRC Letter, Screening and Prioritization Results Regarding Information Pursuant to Title I 0 of the Code of Federal Regulations 50.54(/) Regarding Seismic Hazard Re-evaluations for Recommendation 2.I of the Near-Term Task Force Review of Insights from the Fukushima IchiAccident, dated May 9, 20I4, ADAMS Accession Number MLI4IIIAI47. Document Control Desk PLA-7416 7. NEI Letter, Request for NRC Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), dated July 30, 2015, ADAMS Accession Number ML15223A1 00. 8. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 3002004396, "High Frequency Program: Application Guidance for Functional Confirmation and Fragility, " dated September 17, 2015, ADAMS Accession Number ML15218A569. 9. NRC Letter, Final Determination of Licensee Seismic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(/) Regarding Recommendation 2.1 "Seismic" of the near term Task Force Review of Insights ji*om the Fukushima Dai-chi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015. On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Infmmation per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 indicated that licensees should provide a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of the letter for Central and Eastern United States (CEUS) nuclear power plants. By NRC letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31,2014. By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for Susquehanna Nuclear, LLC (Reference 5). In accordance with the screening, prioritization, and implementation details report (SPID) and Augmented Approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing Individual Plant Examination for External Events (IPEEE) High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required to perform a high frequency confirmation. As noted in the October 27, 2015 letter (Reference 9), Susquehanna Nuclear, LLC is to conduct a limited scope High Frequency Confitmation. Within the May 9, 2014letter (Reference 6), NRC acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, High Frequency Program: Application Guidance for Functional Confitmation and Fragility Evaluation (EPRI 3002004396) for NRC review and endorsement. NRC endorsement was provided by Reference 8. The High Frequency Confirmation for Susquehanna Nuclear, LLC, shows that the GMRS exceedance area between the control point GMRS and IHS anchored at 0.21g is 8.5% over the frequency range of exceedance. As such, the GMRS exceedances are consistent with the criteria identified in Section 3 .1.2 of Reference 7; therefore, no additional  Document Control Desk PLA-7416 evaluation is necessary. The attachment to this letter provides IHS and GMRS information from Reference 5. This transmittal completes the scope of work described in Section 4.2 of Reference 5. This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments. Should you have any questions regarding this submittal, please contact Mr. Jason Jennings at 570-542-3155. I declare under penalty of perjury that the foregoing is true and correct. Executed on: _ ):.__
 
==Enclosure:==
GMRS and SSE Supporting Information Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. J.D. Hughey, NRC Project Manager Mr. M. Shields, PA DEP/BRP Enclosure to PLA-7416 GMRS and IHS Supporting Information (Reference 5) For Susquehanna Steam Electric Station Units 1 & 2 Freq (Hz) 0.1 0.125 0.15 0.2 0.25 0.3 0.35 0.4 0.5 0.6 0.7 0.8 0.9 1 1.25 1.5 2 2.5 3 3.5 4 5 6 7 8 9 10 12.5 15 20 25 30 35 40 50 60 70 80 90 100 Enclosure to PLA-7416 Page 1 of 2 Table 1 GMRS and IHS Data* GMRS IHS@ 0.21g IHS@ 0.30g Accel Freq Accel Freq Accel (g) (Hz) (g) (Hz) (g) 4.66E-03 0.1 0.006 0.1 0.0086 5.82E-03 0.15 0.014 0.15 0.0193 6.98E-03 0.2 0.024 0.2 0.0344 9.31 E-03 0.3 0.054 0.3 0.0773 1.16E-02 0.37 0.075 0.37 0.107 1.40E-02 0.7 0.142 0.7 0.203 1.63E-02 1 0.203 1 0.29 1.86E-02 1.25 0.253 1.25 0.362 2.33E-02 1.5 0.304 1.5 0.435 2.76E-02 1.8 0.365 1.8 0.521 3.23E-02 2 0.406 2 0.579 3.67E-02 2.5 0.445 2.5 0.636 3.97E-02 3.33 0.445 3.33 0.636 4.17E-02 4 0.445 4 0.636 4.89E-02 5 0.445 5 0.636 5.76E-02 5.6 0.445 5.6 0.636 7.08E-02 6.67 0.445 6.67 0.636 8.02E-02 8 0.445 8 0.636 9.79E-02 10 0.396 10 0.565 1.15E-01 13.5 0.337 13.5 0.482 1.31 E-01 20 0.274 20 0.391 1.60E-01 33 0.21 33 0.3 1.80E-01 100 0.21 100 0.3 1.99E-01 2.17E-01 2.31 E-01 2.43E-01 2.49E-01 2.53E-01 2.56E-01 2.49E-01 2.44E-01 2.37E-01 2.22E-01 1.81 E-01 1.50E-01 1.36E-01 1.31 E-01 1.30E-01 1.29E-01
* Data validated against Reference 5 0.7 0.6 0.5 0.4 --c .9).3 ...., tU s... cu -cu t:Jl.2 <( 0.1 0 0.1 -.::: ..... Figure 1 I I I I I I I I I I I I I I I I I I Enclosure to PLA-7416 Page 2 of 2 I I I Comparison of Spectral Accelerations (GMRS & IHS) I I Ill l;-r-ri111, I I I I I I \ I ' I \ I \ . .. * .l I \ I I \ I 1---1) \ \ I \ , ' I I ' I ' ' I I ' I ' ' .. J I I 'I I I 1' -I J,. "f , 'I /1{ rn1* i\ , RS@ 5% da"/ping , , r' , I _...........v t1f' H S *ooho"d ,J 0.3g @ 5% djmptg ,.,..... H S *noho"d 021g iS% I I r i1 1 Frequency (Hz) 10 100 Timothy S. Rausch President and Chief Nuclear Officer Susquehanna Nuclear, LLC 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1504 Timothy.Rausch@talenenergy.com DEC 2 3 2015 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 SUSQUEHANNA STEAM ELECTRIC STATION HIGH FREQUENCY SUPPLEMENT TO SEISMIC HAZARD SCREENING REPORT, RESPONSE TO NRC REQUEST FOR INFORMATION PURSUANT TO ENERGY 10 CFR 50.54 (f) 10 CFR 50.54(F) REGARDING RECOMMENDATION 2.1 OF THE NEAR-TERM TASK FORCE REVIEW OF INSIGHTS FROM THE FUKUSHIMA DAI-ICHI ACCIDENT PLA-7416 Docket No. 50-387 and No. 50-388
 
==References:==
I. NRC Letter, Request for Information Pursuant to Title IO of the Code of Federal Regulations 50.54(/) Regarding Recommendations 2.I, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident, dated March I2, 20I2, ADAMS Accession Number ML12053A340. 2. NRC Letter, Electric Power Research Institute Report 3002000704, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.I: Seismic," as an Acceptable Alternative to the March I2, 20I2, Information Request for Seismic Reevaluations, dated May 7, 20 I3, ADAMS Accession Number MLJ3I06A33I. 3. NEI Letter, Final Draft ofindustly Seismic Evaluation Guidance (EPRI I025287), dated November 27, 20I2, ADAMS Accession Number MLI2333AI68 and ML12333A170. 4. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report I 025287, "Seismic Evaluation Guidance," dated February I5, 2013, ADAMS Accession Number MLI23I9A074. 5. PPL Letter (PLA-7I45), Susquehanna Steam Electric Station Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to IO CFR 50.54(/) Regarding Recommendation 2.I of the Near-Term TaskForce Review of Insights from the Fukushima Dai-ichi Accident, dated March 26, 20I4, ADAMS Accession Number MLI4085A398. 6. NRC Letter, Screening and Prioritization Results Regarding Information Pursuant to Title I 0 of the Code of Federal Regulations 50.54(/) Regarding Seismic Hazard Re-evaluations for Recommendation 2.I of the Near-Term Task Force Review of Insights from the Fukushima IchiAccident, dated May 9, 20I4, ADAMS Accession Number MLI4IIIAI47. Document Control Desk PLA-7416 7. NEI Letter, Request for NRC Endorsement of High Frequency Program: Application Guidance for Functional Confirmation and Fragility Evaluation (EPRI 3002004396), dated July 30, 2015, ADAMS Accession Number ML15223A1 00. 8. NRC Letter, Endorsement of Electric Power Research Institute Final Draft Report 3002004396, "High Frequency Program: Application Guidance for Functional Confirmation and Fragility, " dated September 17, 2015, ADAMS Accession Number ML15218A569. 9. NRC Letter, Final Determination of Licensee Seismic Risk Assessments Under the Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(/) Regarding Recommendation 2.1 "Seismic" of the near term Task Force Review of Insights ji*om the Fukushima Dai-chi Accident, dated October 27, 2015, ADAMS Accession Number ML15194A015. On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued a Request for Infmmation per 10 CFR 50.54(f) (Reference 1) to all power reactor licensees. The required response section of Enclosure 1 indicated that licensees should provide a Seismic Hazard Evaluation and Screening Report within 1.5 years from the date of the letter for Central and Eastern United States (CEUS) nuclear power plants. By NRC letter dated May 7, 2013 (Reference 2), the date to submit the report was extended to March 31,2014. By letter dated May 9, 2014 (Reference 6), the NRC transmitted the results of the screening and prioritization review of the seismic hazards reevaluation submittal for Susquehanna Nuclear, LLC (Reference 5). In accordance with the screening, prioritization, and implementation details report (SPID) and Augmented Approach guidance (References 2, 3 and 4), the reevaluated seismic hazard is used to determine if additional seismic risk evaluations are warranted for a plant. Specifically, the reevaluated horizontal ground motion response spectrum (GMRS) at the control point elevation is compared to the existing Individual Plant Examination for External Events (IPEEE) High Capacity Low Probability of Failure (HCLPF) Spectrum (IHS) to determine if a plant is required to perform a high frequency confirmation. As noted in the October 27, 2015 letter (Reference 9), Susquehanna Nuclear, LLC is to conduct a limited scope High Frequency Confitmation. Within the May 9, 2014letter (Reference 6), NRC acknowledged that these limited scope evaluations will require additional development of the assessment process. By Reference 7, Nuclear Energy Institute (NEI) submitted an Electric Power Research Institute (EPRI) report entitled, High Frequency Program: Application Guidance for Functional Confitmation and Fragility Evaluation (EPRI 3002004396) for NRC review and endorsement. NRC endorsement was provided by Reference 8. The High Frequency Confirmation for Susquehanna Nuclear, LLC, shows that the GMRS exceedance area between the control point GMRS and IHS anchored at 0.21g is 8.5% over the frequency range of exceedance. As such, the GMRS exceedances are consistent with the criteria identified in Section 3 .1.2 of Reference 7; therefore, no additional  Document Control Desk PLA-7416 evaluation is necessary. The attachment to this letter provides IHS and GMRS information from Reference 5. This transmittal completes the scope of work described in Section 4.2 of Reference 5. This letter contains no new Regulatory Commitments and no revision to existing Regulatory Commitments. Should you have any questions regarding this submittal, please contact Mr. Jason Jennings at 570-542-3155. I declare under penalty of perjury that the foregoing is true and correct. Executed on: _ ):.__
 
==Enclosure:==
GMRS and SSE Supporting Information Copy: NRC Region I Mr. J. E. Greives, NRC Sr. Resident Inspector Ms. T. E. Hood, NRC Project Manager Mr. J.D. Hughey, NRC Project Manager Mr. M. Shields, PA DEP/BRP Enclosure to PLA-7416 GMRS and IHS Supporting Information (Reference 5) For Susquehanna Steam Electric Station Units 1 & 2 Freq (Hz) 0.1 0.125 0.15 0.2 0.25 0.3 0.35 0.4 0.5 0.6 0.7 0.8 0.9 1 1.25 1.5 2 2.5 3 3.5 4 5 6 7 8 9 10 12.5 15 20 25 30 35 40 50 60 70 80 90 100 Enclosure to PLA-7416 Page 1 of 2 Table 1 GMRS and IHS Data* GMRS IHS@ 0.21g IHS@ 0.30g Accel Freq Accel Freq Accel (g) (Hz) (g) (Hz) (g) 4.66E-03 0.1 0.006 0.1 0.0086 5.82E-03 0.15 0.014 0.15 0.0193 6.98E-03 0.2 0.024 0.2 0.0344 9.31 E-03 0.3 0.054 0.3 0.0773 1.16E-02 0.37 0.075 0.37 0.107 1.40E-02 0.7 0.142 0.7 0.203 1.63E-02 1 0.203 1 0.29 1.86E-02 1.25 0.253 1.25 0.362 2.33E-02 1.5 0.304 1.5 0.435 2.76E-02 1.8 0.365 1.8 0.521 3.23E-02 2 0.406 2 0.579 3.67E-02 2.5 0.445 2.5 0.636 3.97E-02 3.33 0.445 3.33 0.636 4.17E-02 4 0.445 4 0.636 4.89E-02 5 0.445 5 0.636 5.76E-02 5.6 0.445 5.6 0.636 7.08E-02 6.67 0.445 6.67 0.636 8.02E-02 8 0.445 8 0.636 9.79E-02 10 0.396 10 0.565 1.15E-01 13.5 0.337 13.5 0.482 1.31 E-01 20 0.274 20 0.391 1.60E-01 33 0.21 33 0.3 1.80E-01 100 0.21 100 0.3 1.99E-01 2.17E-01 2.31 E-01 2.43E-01 2.49E-01 2.53E-01 2.56E-01 2.49E-01 2.44E-01 2.37E-01 2.22E-01 1.81 E-01 1.50E-01 1.36E-01 1.31 E-01 1.30E-01 1.29E-01
* Data validated against Reference 5 0.7 0.6 0.5 0.4 --c .9).3 ...., tU s... cu -cu t:Jl.2 <( 0.1 0 0.1 -.::: ..... Figure 1 I I I I I I I I I I I I I I I I I I Enclosure to PLA-7416 Page 2 of 2 I I I Comparison of Spectral Accelerations (GMRS & IHS) I I Ill l;-r-ri111, I I I I I I \ I ' I \ I \ . .. * .l I \ I I \ I 1---1) \ \ I \ , ' I I ' I ' ' I I ' I ' ' .. J I I 'I I I 1' -I J,. "f , 'I /1{ rn1* i\ , RS@ 5% da"/ping , , r' , I _...........v t1f' H S *ooho"d ,J 0.3g @ 5% djmptg ,.,..... H S *noho"d 021g iS% I I r i1 1 Frequency (Hz) 10 100}}

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