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{{Adams
#REDIRECT [[RNP-RA/14-0118, Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes]]
| number = ML14325A645
| issue date = 11/12/2014
| title = Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes (TAC Nos. MF3724, MF3736, MF3737, MF3738, and MF3831)
| author name = Glover R M
| author affiliation = Duke Energy Carolinas, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000261
| license number = DPR-023
| contact person =
| case reference number = RNP-RA/14-0118, TAC MF3724, TAC MF3736, TAC MF3737, TAC MF3738
| document type = Letter, Request for Additional Information (RAI)
| page count = 23
| project = TAC:MF3724, TAC:MF3736, TAC:MF3737, TAC:MF3738
}}
 
=Text=
{{#Wiki_filter:~ENERGY.R. Michael GloverH. B. Robinson SteamElectric Plant Unit 2Site Vice PresidentDuke Energy Progress3581 West Entrance RoadHartsville, SC 295500:843 857 1704F: 843 857 1319Mike. Glover@duke-energy.conNovember 12, 2014Serial: RNP-RA/14-011810 CFR 50.54(f)ATTN: Document Control DeskU. S. Nuclear Regulatory CommissionWashington, DC 20555-0001H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23Subject: Response to Request for Additional Information Associated with Near-Term Task ForceRecommendation 2.1, Seismic Re-Evaluations Related to Southeastern CatalogChanges (TAC NOS. MF3724, MF3736, MF3737, MF3738, and MF3831)References:1. NRC Letter, Request for Information Pursuant to Title 10 of the Code of FederalRegulations 50.54() Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-TermTask Force Review of Insights from the Fukushima Dai-ichi Accident, dated March 12,2012, (ADAMS Accession No. ML12053A340)2. NRC letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic EvaluationGuidance," dated February 15, 2013 (ADAMS Accession Number ML12319A074)3. EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritization andImplementation Details (SPID) for the Resolution of Fukushima Near-Term Task ForceRecommendation 2.1: Seismic, dated February 2013 (ADAMS Accession NumberML12333A170)4. NEI letter, Proposed Path Forward for NTTF Recommendation 2.1: SeismicReevaluations, dated April 9, 2013 (ADAMS Accession Number ML13101A379)5. NRC letter, Electric Power Research Institute Final Draft Report XXXXXX, "SeismicEvaluation Guidance: Augmented Approach for the Resolution of Fukushima Near-TermTask Force Recommendation 2.1: Seismic, " as an Acceptable Alternative to the March12, 2012, Information Request for Seismic Reevaluations, dated May 7, 2013 (ADAMSAccession Number ML13106A331)6. NEI Letter, Seismic Evaluations for Plants in the Central and Eastern United States,dated March 12, 2014 (ADAMS Accession Nos. ML14083A584, ML14083A586 andML14083A587)7. Duke Energy letter to NRC, Seismic Hazard Evaluation, Response to NRC 10 CFR50.54(f Request for Information Pursuant to Title 10 of the Code of Federal Regulations50.54(o Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task ForceReview of Insights from the Fukushima Dai-ichi Accident, dated March 31, 2014(ADAMS Accession No. ML14099A204)8. NRC letter, Request for Additional Information Associated with Near-Term Task ForceRecommendation 2.1, Seismic Re-Evaluations Related Southeastern CatalogueChanges (TAC NOS. MF3724, MF 3736, MF3737, MF3738, and MF3831), datedOctober 23, 2014 (ADAMS Accession No. ML14268A516)/ '
Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionLadies and Gentlemen:On March 12, 2012, the Nuclear Regulatory Commission (NRC) issued Reference 1 to all powerreactor licensees and holders of construction permits in active or deferred status. Enclosure 1 ofReference 1 requested each addressee in the Central and Eastern United States (CEUS) tosubmit a written response consistent with the requested seismic hazard evaluation informationby September 12, 2013. By letter dated February 15, 2013, the NRC issued Reference 2,endorsing the Reference 3 industry guidance for responding to the seismic evaluation in Reference1. Section 4 of Reference 3 identified the detailed information to be included in the seismic hazardevaluation submittals.On April 9, 2013, the Nuclear Energy Institute (NEI) submitted Reference 4 to the NRC, requestingNRC agreement to delay submittal of part of the CEUS seismic hazard evaluation information sothat an update to the Electric Power Research Institute (EPRI) (2004, 2006) ground motionattenuation model could be completed and used to develop that information. NEI proposed thatdescriptions of subsurface materials and properties and base case velocity profiles (items 3a and3b in Section 4 of Reference 3) be submitted to the NRC by September 12, 2013, with theremaining seismic hazard and screening information submitted to the NRC by March 31, 2014. InReference 5, the NRC agreed with this recommendation.Reference 3 contains industry guidance and detailed information to be included in the SeismicHazard Evaluation submittals. The previously submitted Seismic Hazard Evaluation for H. B.Robinson Steam Electric Plant, Unit No. 2 provided the information described in Section 4 ofReference 3 in accordance with the schedule identified in Reference 4. As discussed in theEnclosure to the March 31, 2014, submittal letter (Reference 7), seismic hazard curves and aGround Motion Response Spectrum (GMRS) were developed using current methodology. ThatGMRS was compared to the design basis Safe Shutdown Earthquake (SSE) response spectrumthat was included in that submittal.As discussed within Reference 1, NRC acknowledged that the current regulatory approach and theresultant plant capabilities provides reasonable confidence that an accident with consequencessimilar to the Fukushima event is unlikely with nuclear power plants located in the United States.The NRC concluded that continued plant operation does not pose an imminent risk to the publichealth and safety.By letter dated March 12, 2014 (Reference 6), NEI provided the NRC with seismic core damagerisk estimates based on updated seismic hazard information as it applies to operating nuclearreactors in the CEUS, which includes H. B. Robinson Steam Electric Plant, Unit No. 2. These riskassessments continue to support the conclusions of the NRC Generic Issue-1 99 "Safety/RiskAssessment" and indicate that current seismic design of operating reactors provide adequateprotection and safety margin to withstand potential earthquakes that exceed the original designbasis.The Enclosure to this letter provides Duke Energy's response to the NRC's Request for AdditionalInformation (RAI) (Reference 8) for H. B. Robinson, Unit No. 2.This letter contains no new regulatory commitments.
Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionIf you have any questions or require additional information, please contact Richard Hightower,Manager, Nuclear Regulatory Affairs at (843)-857-1329.I declare under the penalty of perjury that the foregoing is true and correct.Executed onAJ OVgV4c~r(9.21Sincerely,R. Michael GloverSite Vice PresidentRMG/shcEnclosure:Duke Energy Response to NRC RAI Regarding H. B. Robinson, Unit No. 2cc: Ms. M. C. Barillas, NRC Project Manager, NRRMr. K. M. Ellis, NRC Senior Resident InspectorMr. V. M. McCree, NRC Region II Administrator
 
==Enclosure==
to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionENCLOSUREDUKE ENERGY RESPONSE TONRC REQUEST FOR ADDITIONAL INFORMATIONH. B. ROBINSON, UNIT NO. 2
 
==Enclosure==
to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionReview of Deviation from CEUS Seismic Source Characterization Cataloq Version 7.0By letter dated March 12, 2012 (Agencywide Documents Access and Management System(ADAMS) Accession No. ML 12053A340), the NRC staff requested that licensees whose plants arelocated in the central and eastern United States (CEUS) use the recently published Central andEastern United States Seismic Source Characterization for Nuclear Facilities (CEUS-SSC) toconduct the seismic hazard reevaluations. Specifically, Attachment 1 to "Seismic" Enclosure 1 ofthe March 12, 2012, letter stated that "regional and local refinements of the CEUS-SSC are notnecessary for this evaluation." The staffs endorsement of the CEUS-SSC without refinement wasintended to expedite the Near-Term Task Force (NTTF) 2.1 seismic hazard reevaluations and toensure efficient use of NRC and licensee resources.By letter dated February 15, 2013 (ADAMS Accession No. ML 12319A074), "Endorsement ofElectric Power Research Institute [EPRI] Final Draft Report 1025287, 'Seismic EvaluationGuidance: Screening, Prioritization and Implementation Details (SPID),' the NRC staff endorsedusing the SPID guidance.Regarding the use of the CEUS-SSC for the NTTF Recommendation 2.1 seismic hazardreevaluations, Section 2 of the SPID states:For site-specific licensing applications or site-specific safety decisions, these seismicsources would be reviewed on a site-specific basis to determine if they need to beupdated. Such evaluations would be appropriate in a licensing application, wherefocus could be made on site-specific applications. However, for a screening-levelstudy of multiple plants for the purpose of setting priorities, the use of these seismicsources as published is appropriate.The CEUS-SSC was published as NUREG-2115, DOE/NE-0140, EPRI 1021097, "Central andEastern United States Seismic Source Characterization for Nuclear Facilities," January 2012(ADAMS Accession No. ML 12048A776) and conducted using a Senior Seismic Hazard AnalysisCommittee (SSHAC) Level 3 study, consistent with NUREG/CR-6372, "Recommendations forProbabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts," April1997(ADAMS Accession Nos. ML080090003 and ML080090004, respectively). The CEUS-SSC expertpanel review considered the present state of knowledge of the Charleston seismic zone and knownnontectonic events including reservoir-induced events in developing the seismic catalog for theCEUS-SSC. Section 6 of NUREG-2117, "Practical Implementation Guidelines for SSHAC Level 3and 4 Hazard Studies: Rev. 1," Office of Nuclear Regulatory Research, 2012, (ADAMS AccessionNo. ML 12118A445) recommends that viable regional probabilistic hazard studies, such as theCEUS-SSC, should be updated with at least a SSHAC Level 2 study.By letters dated March 31, 2014, and by letter dated March 26, 2014, to the NRC, Duke EnergyProgress, Inc. and Duke Energy Carolinas, LLC, the licensees for H. B. Robinson Steam ElectricPlant, Unit No. 2 (Robinson) and Oconee Nuclear Station, Units 1, 2, and 3 (Oconee); and SouthCarolina Electric and Gas Company, the licensee for Virgil C. Summer Nuclear Station, Unit 1 (VCSummer), submitted a revision to the CEUS-SSC catalog as part of the reevaluated seismic hazardsubmittal. Subsequently, by letter dated August 28, 2014 (ADAMS Accession No. ML 14260A200),EPRI provided a report containing CEUS-SSC Catalog Version 8.0 following, "Review of NUREG-2115 Earthquake catalog with regard to identification of additional Reservoir Induced Seismicity(RIS) earthquakes in the southeastern United States and locations of earthquakes in SouthCarolina near the time of the 1886 Charleston, SC earthquake sequence," dated March 5, 2014.Note the staff does not consider the proposed catalog update to be a new version of the CEUS-SSC Catalog but rather a regional update specifically made for the Recommendation 2.1 seismichazard reevaluations of H. B. Robinson, Oconee, and VC Summer plant sites.
 
==Enclosure==
to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionRequest for Additional InformationConsistent with the 10 CFR 50.54(f) request for information and the SPID guidance, please providea revised March 2014 seismic hazard reevaluation submittal reflecting the staff endorsed CEUS-SSC Catalog Version 7.0. Alternatively, to ensure that the regional catalog update made for theRecommendation 2.1 seismic hazard reevaluations of H.B. Robinson, Oconee, and VC Summerplant sites represents the center, body, and range of the technically defensible interpretations,please provide a SSHAC Level 2 study. In addition to providing a detailed description of the catalogupdate, please describe the scope of the update and whether you also considered the impact ofearthquakes in the region since the time period covered by the CEUS-SSC Catalog.Please include in the response, in table form, control point seismic hazard curves developed usingboth the currently-endorsed CEUS-SSC catalog as well as the proposed updated regional catalogused for the Recommendation 2.1 seismic hazard reevaluations of H.B. Robinson, Oconee, andVC Summer plant sites.H. B. Robinson ResponseH. B. Robinson Steam Electric Plant, Unit No. 2 has decided not to provide a revised March 2014seismic hazard reevaluation submittal reflecting the staff endorsed CEUS-SSC Catalog Version7.0, but has instead opted to provide the proposed alternative as provided by the NRC Request forAdditional Information (RAI).The NRC RAI points out that the Electric Power Research Institute (EPRI) guidance document,Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID),identifies an approved seismicity catalog and that industry was expected to used it. However, theRAI does not address the expectations communicated in the NRC endorsement letter to theindustry dated February 15, 2013 (ADAMS Accession No. ML1 2319A074), "Endorsement ofElectric Power Research Institute [EPRI] Final Draft Report 1025287, 'Seismic EvaluationGuidance: Screening, Prioritization and Implementation Details (SPID),' in which the NRC staffstated:If a significant earthquake in the CEUS were to occur or new information were to emergeduring the reevaluation period that could require an update of the CEUS-SSC model, thestaff expects licensees to evaluate the significance of the new information to determine ifthe CEUS-SSC model needs to be updated in order to appropriately respond to the 50.54(f)request.The NRC interprets the catalog change as requiring an industry review (SSHAC Level 2) thatexceeds the review already performed. H. B. Robinson Steam Electric Plant, Unit No. 2 will creditthe SSHAC Level 2 Study of the updated Regional CEUS-SSC Catalog. Duke Energy expects theresults of the SSHAC Level 2 Study to be submitted to the NRC by April 30, 2015.In addition the detailed description of the CEUS-SSC Catalog update was submitted to the NRC byan EPRI letter dated August 28, 2014 (ADAMS Accession No. ML14260A209). The scope of theupdate of the catalog was performed with regard to two issues: (1) identification of additionalreservoir induced seismicity (RIS) earthquakes in the southeastern US and (2) locations ofearthquakes in South Carolina near the time of the 1886 Charleston, SC earthquake sequence.After removal of the RIS earthquakes and correcting the parameters of the Charleston aftershocks,processing of the updated earthquake catalog was performed using the same procedures asperformed in EPRI 1021097 including Magnitude evaluations, de-clustering, and completenesscalculations. This limited scope update was completed without including the impact of earthquakesin the region since the time period covered by the CEUS-SSC Catalog.
 
==Enclosure==
to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionAttachments 1 and 2 to the Enclosure provide, in table form, control point seismic hazard curvesdeveloped using both the currently-endorsed CEUS-SSC catalog as well as the proposed updatedregional catalog used for the Recommendation 2.1 seismic hazard reevaluation for H. B. RobinsonSteam Electric Plant, Unit No. 2.Therefore, Duke Energy has determined that the best approach for H. B. Robinson Steam ElectricPlant, Unit No. 2 is to continue development of seismic hazard and GMRS using measured shearwave velocity and the latest Industry information and guidance. Results of the effort describedduring the June 30, 2014 Public Meeting will be provided to NRC as early as possible(approximately First Quarter 2015). Consideration of earthquakes since the time period covered bythe CEUS-SSC Catalog will be performed as part of our Recommendation 2.1 site specific seismichazard effort.
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory Commission(8 pages including this cover)ATTACHMENT 1H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2SEISMIC HAZARD CURVES IN TABLE FORMAT FROM THE CURRENTLY ENDORSEDCEUS-SSC CATALOG
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionSeismic Hazard Curves in Table Format using CEUS-SSC Catalog, Version 7.0Table A-la. Mean and Fractile Seismic Hazard Curves for PGA at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.12E-02 3.84E-02 4.50E-02 5.20E-02 5.75E-02 6.09E-020.001 4.67E-02 3.09E-02 4.01 E-02 4.77E-02 5.35E-02 5.75E-020.005 2.63E-02 1.34E-02 1.98E-02 2.60E-02 3.33E-02 3.90E-020.01 1.71 E-02 8.47E-03 1.18E-02 1.64E-02 2.19E-02 2.88E-020.015 1.27E-02 6.17E-03 8.35E-03 1.20E-02 1.62E-02 2.32E-020.03 6.95E-03 3.09E-03 4.19E-03 6.36E-03 9.11E-03 1.40E-020.05 .4.19E-03 1.53E-03 2.22E-03 3.73E-03 5.83E-03 9.11E-030.075 2.67E-03 7.55E-04 1.20E-03 2.25E-03 4.01 E-03 6.26E-030.1 1.87E-03 4.13E-04 6.93E-04 1.49E-03 2.96E-03 4.77E-030.15 1.03E-03 1.60E-04 2.80E-04 7.03E-04 1.77E-03 3.05E-030.3 2.72E-04 2.13E-05 4.25E-05 1.29E-04 4.63E-04 1.02E-030.5 7.88E-05 3.01E-06 7.55E-06 3.19E-05 1.18E-04 3.09E-040.75 2.51 E-05 5.42E-07 1.69E-06 9.51 E-06 3.68E-05 9.51 E-051. 1.02E-05 1.57E-07 6.09E-07 3.68E-06 1.57E-05 3.73E-051.5 2.58E-06 2.76E-08 1.34E-07 8.35E-07 4.25E-06 9.93E-063. 2.09E-07 9.11E-10 4.98E-09 5.12E-08 3.42E-07 8.98E-075. 3.13E-08 1.42E-10 3.68E-10 5.35E-09 4.50E-08 1.38E-077.5 6.48E-09 1.04E-10 1.42E-10 8.23E-10 7.89E-09 2.92E-0810. 1.98E-09 1.01E-10 1.32E-10 2.64E-10 2.1OE-09 9.11E-09
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-i b. Mean and Fractile Seismic Hazard Curves for 25 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.23E-02 4.13E-02 4.70E-02 5.27E-02 5.83E-02 6.17E-020.001 4.90E-02 3.57E-02 4.31 E-02 4.98E-02 5.50E-02 5.91 E-020.005 3.15E-02 1.84E-02 2.53E-02 3.14E-02 3.79E-02 4.43E-020.01 2.25E-02 1.23E-02 1.69E-02 2.19E-02 2.76E-02 3.52E-020.015 1.77E-02 9.51E-03 1.29E-02 1.69E-02 2.19E-02 2.96E-020.03 1.08E-02 5.58E-03 7.34E-03 1.02E-02 1.36E-02 1.95E-020.05 6.96E-03 3.23E-03 4.37E-03 6.45E-03 9.24E-03 1.31 E-020.075 4.64E-03 1.84E-03 2.64E-03 4.25E-03 6.45E-03 9.11 E-030.1 3.37E-03 1.13E-03 1.72E-03 3.01E-03 4.90E-03 6.93E-030.15 2.04E-03 4.77E-04 8.12E-04 1.72E-03 3.23E-03 4.70E-030.3 7.09E-04 6.83E-05 1.44E-04 4.70E-04 1.25E-03 2.16E-030.5 2.72E-04 1.57E-05 3.52E-05 1.44E-04 4.83E-04 9.79E-040.75 1.11E-04 5.83E-06 1.29E-05 5.20E-05 1.84E-04 4.13E-041. 5.35E-05 2.88E-06 6.64E-06 2.32E-05 8.72E-05 1.98E-041.5 1.68E-05 9.65E-07 2.25E-06 6.73E-06 2.76E-05 6.09E-053. 1.69E-06 3.95E-08 1.42E-07 8.12E-07 3.05E-06 6.17E-065. 3.34E-07 1.46E-09 1.07E-08 1.27E-07 6.26E-07 1.38E-067.5 1.22E-07 1.69E-10 1.20E-09 1.95E-08 2.29E-07 5.91 E-0710. 6.58E-08 1.32E-10 2.80E-10 4.50E-09 1.21E-07 3.42E-07
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-ic. Mean and Fractile Seismic Hazard Curves for 10 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.37E-02 4.50E-02 4.83E-02 5.35E-02 5.91 E-02 6.26E-020.001 5.16E-02 4.19E-02 4.63E-02 5.20E-02 5.66E-02 6.09E-020.005 3.62E-02 2.42E-02 2.96E-02 3.63E-02 4.25E-02 4.70E-020.01 2.62E-02 1.60E-02 2.01 E-02 2.60E-02 3.23E-02 3.68E-020.015 2.06E-02 1.18E-02 1.53E-02 2.01E-02 2.57E-02 3.05E-020.03 1.24E-02 6.73E-03 8.72E-03 1.20E-02 1.60E-02 2.01 E-020.05 8.02E-03 4.13E-03 5.35E-03 7.66E-03 1.05E-02 1.36E-020.075 5.45E-03 2.57E-03 3.47E-03 5.12E-03 7.34E-03 9.51E-030.1 4.05E-03 1.74E-03 2.42E-03 3.79E-03 5.58E-03 7.34E-030.15 2.57E-03 8.98E-04 1.34E-03 2.35E-03 3.79E-03 5.12E-030.3 9.90E-04 2.10E-04 3.57E-04 8.OOE-04 1.62E-03 2.46E-030.5 3.93E-04 5.20E-05 9.79E-05 2.64E-04 6.73E-04 1.18E-030.75 1.62E-04 1.34E-05 2.76E-05 9.24E-05 2.80E-04 5.50E-041. 7.93E-05 4.63E-06 1.04E-05 4.07E-05 1.36E-04 2.84E-041.5 2.59E-05 9.79E-07 2.49E-06 1.18E-05 4.37E-05 9.51E-053. 2.82E-06 7.77E-08 2.49E-07 1.01 E-06 4.83E-06 1.11E-055. 4.60E-07 8.47E-09 2.92E-08 1.53E-07 8.OOE-07 1.90E-067.5 1.06E-07 8.60E-10 4.01E-09 3.47E-08 1.84E-07 4.50E-0710. 3.88E-08 2.04E-10 9.51E-10 1.15E-08 6.45E-08 1.72E-07
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-id. Mean and Fractile Seismic Hazard Curves for 5 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.41E-02 4.50E-02 4.90E-02 5.42E-02 5.91E-02 6.26E-020.001 5.27E-02 4.31E-02 4.77E-02 5.27E-02 5.83E-02 6.17E-020.005 3.93E-02 2.68E-02 3.19E-02 3.95E-02 4.63E-02 5.05E-020.01 2.89E-02 1.72E-02 2.19E-02 2.88E-02 3.57E-02 4.01E-020.015 2.26E-02 1.27E-02 1.67E-02 2.25E-02 2.88E-02 3.23E-020.03 1.32E-02 6.93E-03 9.24E-03 1.29E-02 1.72E-02 2.04E-020.05 8.16E-03 4.25E-03 5.58E-03 7.89E-03 1.08E-02 1.31 E-020.075 5.39E-03 2.64E-03 3.52E-03 5.12E-03 7.23E-03 8.85E-030.1 3.97E-03 1.79E-03 2.46E-03 3.79E-03 5.42E-03 6.73E-030.15 2.51E-03 9.37E-04 1.38E-03 2.35E-03 3.63E-03 4.63E-030.3 9.78E-04 2.32E-04 3.90E-04 8.23E-04 1.57E-03 2.29E-030.5 3.90E-04 6.09E-05 1.11E-04 2.76E-04 6.64E-04 1.11E-030.75 1.59E-04 1.62E-05 3.19E-05 9.37E-05 2.68E-04 5.27E-041. 7.70E-05 5.35E-06 1.13E-05 3.95E-05 1.29E-04 2.76E-041.5 2.49E-05 8.60E-07 2.1OE-06 1.07E-05 4.01E-05 9.37E-053. 2.72E-06 2.72E-08 1.08E-07 8.60E-07 4.43E-06 1.07E-055. 4.30E-07 2.22E-09 1.32E-08 1.04E-07 7.13E-07 1.84E-067.5 9.06E-08 3.68E-10 1.95E-09 1.77E-08 1.46E-07 4.13E-0710. 2.91E-08 1.60E-10 4.83E-10 4.83E-09 4.43E-08 1.34E-07
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-le. Mean and Fractile Seismic Hazard Curves for 2.5 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.31E-02 4.37E-02 4.77E-02 5.35E-02 5.83E-02 6.17E-020.001 5.OOE-02 3.84E-02 4.37E-02 5.05E-02 5.66E-02 6.OOE-020.005 3.15E-02 1.72E-02 2.19E-02 3.09E-02 4.13E-02 4.63E-020.01 2.09E-02 9.79E-03 1.29E-02 2.01 E-02 2.92E-02 3.47E-020.015 1.54E-02 6.54E-03 8.85E-03 1.46E-02 2.19E-02 2.68E-020.03 8.15E-03 2.92E-03 4.25E-03 7.55E-03 1.21 E-02 1.53E-020.05 4.76E-03 1.49E-03 2.32E-03 4.37E-03 7.13E-03 9.37E-030.075 3.03E-03 8.OOE-04 1.36E-03 2.76E-03 4.70E-03 6.17E-030.1 2.18E-03 4.90E-04 8.85E-04 1.95E-03 3.47E-03 4.70E-030.15 1.32E-03 2.22E-04 4.37E-04 1.11E-03 2.22E-03 3.14E-030.3 4.68E-04 4.43E-05 9.51 E-05 3.14E-04 8.35E-04 1.44E-030.5 1.72E-04 1.07E-05 2.39E-05 8.72E-05 3.01E-04 6.26E-040.75 6.56E-05 2.96E-06 6.83E-06 2.64E-05 1.04E-04 2.60E-041. 3.01 E-05 1.08E-06 2.60E-06 1.04E-05 4.37E-05 1.20E-041.5 8.81E-06 2.22E-07 5.83E-07 2.60E-06 1.13E-05 3.37E-053. 7.91E-07 8.98E-09 3.14E-08 1.98E-07 1.01 E-06 2.80E-065. 1.17E-07 6.17E-10 2.57E-09 2.35E-08 1.60E-07 4.70E-077.5 2.54E-08 1.53E-10 3.57E-10 3.73E-09 3.42E-08 1.13E-0710. 8.66E-09 1.23E-10 1.55E-10 9.79E-10 1.07E-08 4.01E-08
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-If. Mean and Fractile Seismic Hazard Curves for 1 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 4.04E-02 2.32E-02 2.96E-02 4.13E-02 5.05E-02 5.50E-020.001 3.1OE-02 1.49E-02 2.01E-02 3.09E-02 4.19E-02 4.77E-020.005 1.12E-02 3.73E-03 5.66E-03 1.05E-02 1.67E-02 2.07E-020.01 6.33E-03 1.67E-03 2.76E-03 5.83E-03 9.79E-03 1.27E-020.015 4.38E-03 9.11E-04 1.67E-03 3.90E-03 7.03E-03 9.51E-030.03 2.12E-03 2.46E-04 5.50E-04 1.74E-03 3.68E-03 5.35E-030.05 1.14E-03 7.23E-05 1.92E-04 8.47E-04 2.10E-03 3.23E-030.075 6.58E-04 2.35E-05 7.03E-05 4.31E-04 1.27E-03 2.07E-030.1 4.30E-04 1.01 E-05 3.23E-05 2.46E-04 8.35E-04 1.49E-030.15 2.25E-04 2.96E-06 1.02E-05 1.04E-04 4.37E-04 8.72E-040.3 6.20E-05 3.90E-07 1.49E-06 1.79E-05 1.07E-04 2.76E-040.5 2.03E-05 9.79E-08 4.19E-07 4.37E-06 3.05E-05 9.24E-050.75 7.44E-06 3.37E-08 1.55E-07 1.36E-06 9.93E-06 3.37E-051. 3.41 E-06 1.57E-08 7.23E-08 5.91 E-07 4.31 E-06 1.51 E-051.5 1.04E-06 4.77E-09 2.32E-08 1.79E-07 1.27E-06 4.50E-063. 1.15E-07 5.20E-10 2.53E-09 2.01E-08 1.46E-07 5.12E-075. 2.21E-08 1.57E-10 4.37E-10 3.33E-09 2.72E-08 1.01 E-077.5 6.OOE-09 1.32E-10 1.62E-10 7.89E-10 6.64E-09 2.68E-0810. 2.34E-09 1.01E-10 1.32E-10 3.09E-10 2.39E-09 1.02E-08
 
==Attachment==
1 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-lg. Mean andFractile Seismic Hazard Curves for 0.5 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 2.28E-02 1.34E-02 1.72E-02 2.25E-02 2.84E-02 3.33E-020.001 1.48E-02 8.OOE-03 1.05E-02 1.44E-02 1.90E-02 2.32E-020.005 5.01 E-03 1.72E-03 2.68E-03 4.63E-03 7.34E-03 9.37E-030.01 2.81E-03 6.45E-04 1.16E-03 2.46E-03 4.50E-03 6.17E-030.015 1.83E-03 3.09E-04 6.26E-04 1.49E-03 3.05E-03 4.50E-030.03 7.19E-04 6.36E-05 1.57E-04 4.90E-04 1.27E-03 2.16E-030.05 3.08E-04 1.60E-05 4.31E-05 1.67E-04 5.58E-04 1.10E-030.075 1.45E-04 4.77E-06 1.34E-05 5.91 E-05 2.53E-04 5.83E-040.1 8.13E-05 1.92E-06 5.50E-06 2.64E-05 1.34E-04 3.52E-040.15 3.44E-05 4.98E-07 1.49E-06 7.77E-06 4.90E-05 1.60E-040.3 7.08E-06 3.73E-08 1.34E-07 8.60E-07 7.13E-06 3.19E-050.5 2.03E-06 4.25E-09 1.95E-08 1.72E-07 1.62E-06 8.47E-060.75 7.21E-07 7.13E-10 3.73E-09 4.63E-08 5.05E-07 2.96E-061. 3.37E-07 2.42E-10 1.16E-09 1.79E-08 2.22E-07 1.38E-061.5 1.12E-07 1.32E-10 2.64E-10 4.50E-09 6.83E-08 4.56E-073. 1.53E-08 1.01E-10 1.32E-10 4.37E-10 8.12E-09 6.17E-085. 3.19E-09 9.11E-11 1.04E-10 1.51E-10 1.44E-09 1.20E-087.5 8.38E-10 9.11E-11 1.01E-10 1.32E-10 3.95E-10 2.88E-0910. 3.06E-10 9.11E-11 1.01E-10 1.32E-10 1.98E-10 1.05E-09Above Tables were developed for H. B. Robinson Steam Electric Plant, Unit No. 2 reflectinginformation from the staff endorsed CEUS-SSC Catalog Version 7.0
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory Commission(8 pages including this cover)ATTACHMENT 2H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2SEISMIC HAZARD CURVES IN TABLE FORMAT USING CORRECTED REGIONAL CEUS-SSCCATALOG FOR THE RECOMMENDATION 2.1 SEISMIC HAZARD REEVALUATION
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionSeismic Hazard Curves in Table Format using Corrected RegionalCEUS-SSC Catalog for the Recommendation 2.1 Seismic Hazard ReevaluationTable A-la. Mean and Fractile Seismic Hazard Curves for PGA at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 4.87E-02 3.68E-02 4.31 E-02 4.90E-02 5.50E-02 5.83E-020.001 4.43E-02 2.92E-02 3.79E-02 4.50E-02 5.12E-02 5.50E-020.005 2.44E-02 1.21 E-02 1.82E-02 2.42E-02 3.09E-02 3.68E-020.01 1.56E-02 7.55E-03 1.07E-02 1.51 E-02 2.01E-02 2.68E-020.015 1.15E-02 5.42E-03 7.45E-03 1.08E-02 1.46E-02 2.13E-020.03 6.20E-03 2.64E-03 3.68E-03 5.66E-03 8.12E-03 1.29E-020.05 3.72E-03 1.29E-03 1.92E-03 3.28E-03 5.27E-03 8.12E-030.075 2.38E-03 6.09E-04 1.02E-03 2.01 E-03 3.63E-03 5.66E-030.1 1.66E-03 3.28E-04 5.83E-04 1.31 E-03 2.68E-03 4.31E-030.15 9.09E-04 1.20E-04 2.22E-04 6.09E-04 1.60E-03 2.76E-030.3 2.33E-04 1.42E-05 2.96E-05 9.93E-05 4.01 E-04 9.24E-040.5 6.44E-05 1.95E-06 4.98E-06 2.13E-05 9.24E-05 2.68E-040.75 1.94E-05 3.33E-07 1.07E-06 6.17E-06 2.60E-05 7.45E-051. 7.51 E-06 9.93E-08 3.68E-07 2.32E-06 1.04E-05 2.80E-051.5 1.76E-06 1.82E-08 8.12E-08 5.05E-07 2.64E-06 6.73E-063. 1.29E-07 6.73E-10 3.28E-09 3.05E-08 2.07E-07 5.50E-075. 1.90E-08 1.32E-10 2.84E-10 3.19E-09 2.64E-08 8.35E-087.5 3.92E-09 1.01E-10 1.32E-10 5.27E-10 4.63E-09 1.77E-0810. 1.19E-09 9.37E-11 1.23E-10 2.01E-10 1.32E-09 5.58E-09
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-I b. Mean and Fractile Seismic Hazard Curves for 25 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 4.98E-02 3.95E-02 4.43E-02 5.05E-02 5.50E-02 5.83E-020.001 4.65E-02 3.42E-02 4.07E-02 4.70E-02 5.27E-02 5.58E-020.005 2.94E-02 1.69E-02 2.32E-02 2.92E-02 3.57E-02 4.13E-020.01 2.07E-02 1.13E-02 1.53E-02 2.01E-02 2.53E-02 3.28E-020.015 1.62E-02 8.47E-03 1.16E-02 1.55E-02 1.98E-02 2.76E-020.03 9.73E-03 4.83E-03 6.54E-03 9.11E-03 1.23E-02 1.79E-020.05 6.19E-03 2.80E-03 3.79E-03 5.75E-03 8.23E-03 1.18E-020.075 4.11E-03 1.55E-03 2.25E-03 3.73E-03 5.75E-03 8.12E-030.1 2.98E-03 9.24E-04 1.46E-03 2.68E-03 4.37E-03 6.26E-030.15 1.80E-03 3.84E-04 6.73E-04 1.51 E-03 2.88E-03 4.25E-030.3 6.20E-04 5.05E-05 1.11E-04 3.95E-04 1.11E-03 1.98E-030.5 2.33E-04 1.02E-05 2.46E-05 1.13E-04 4.13E-04 8.72E-040.75 9.18E-05 3.63E-06 8.47E-06 3.73E-05 1.51 E-04 3.63E-041. 4.30E-05 1.87E-06 4.13E-06 1.57E-05 6.64E-05 1.67E-041.5 1.27E-05 6.09E-07 1.38E-06 4.50E-06 1.95E-05 4.70E-053. 1.13E-06 2.60E-08 8.60E-08 4.77E-07 1.95E-06 4.13E-065. 2.1OE-07 1.05E-09 6.45E-09 7.55E-08 3.95E-07 8.47E-077.5 7.50E-08 1.53E-10 7.55E-10 1.21E-08 1.32E-07 3.57E-0710. 4.03E-08 1.32E-10 2.13E-10 2.84E-09 6.93E-08 2.07E-07
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-ic. Mean and Fractile Seismic Hazard Curves for 10 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.11E-02 4.25E-02 4.56E-02 5.12E-02 5.66E-02 5.91E-020.001 4.91E-02 4.01E-02 4.37E-02 4.90E-02 5.42E-02 5.75E-020.005 3.40E-02 2.29E-02 2.76E-02 3.42E-02 4.01 E-02 4.43E-020.01 2.43E-02 1.46E-02 1.84E-02 2.42E-02 3.01 E-02 3.47E-020.015 1.89E-02 1.08E-02 1.38E-02 1.87E-02 2.35E-02 2.84E-020.03 1.13E-02 6.OOE-03 7.77E-03 1.08E-02 1.44E-02 1.84E-020.05 7.18E-03 3.57E-03 4.77E-03 6.83E-03 9.37E-03 1.21E-020.075 4.85E-03 2.19E-03 3.01E-03 4.56E-03 6.54E-03 8.60E-030.1 3.61E-03 1.46E-03 2.1OE-03 3.37E-03 5.05E-03 6.64E-030.15 2.29E-03 7.34E-04 1.15E-03 2.07E-03 3.42E-03 4.63E-030.3 8.80E-04 1.64E-04 2.96E-04 6.93E-04 1.46E-03 2.25E-030.5 3.44E-04 3.90E-05 7.55E-05 2.22E-04 6.OOE-04 1.08E-030.75 1.38E-04 9.51E-06 2.04E-05 7.23E-05 2.42E-04 4.90E-041. 6.63E-05 3.14E-06 7.23E-06 3.05E-05 1.11E-04 2.49E-041.5 2.06E-05 6.45E-07 1.62E-06 8.12E-06 3.33E-05 7.89E-053. 2.01 E-06 4.98E-08 1.51 E-07 6.54E-07 3.28E-06 8.OOE-065. 3.02E-07 5.66E-09 1.84E-08 9.51E-08 5.12E-07 1.23E-067.5 6.66E-08 6.OOE-10 2.46E-09 2.07E-08 1.15E-07 2.76E-0710. 2.39E-08 1.74E-10 6.09E-10 6.93E-09 4.07E-08 1.05E-07
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-id. Mean and Fractile Seismic Hazard Curves for 5 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.15E-02 4.31E-02 4.63E-02 5.20E-02 5.66E-02 6.00E-020.001 5.02E-02 4.13E-02 4.50E-02 5.05E-02 5.50E-02 5.83E-020.005 3.70E-02 2.49E-02 2.96E-02 3.73E-02 4.43E-02 4.83E-020.01 2.70E-02 1.60E-02 2.04E-02 2.68E-02 3.37E-02 3.73E-020.015 2.10E-02 1.16E-02 1.53E-02 2.07E-02 2.68E-02 3.05E-020.03 1.20E-02 6.26E-03 8.35E-03 1.16E-02 1.57E-02 1.87E-020.05 7.36E-03 3.73E-03 4.98E-03 7.13E-03 9.79E-03 1.20E-020.075 4.85E-03 2.29E-03 3.09E-03 4.63E-03 6.54E-03 8.12E-030.1 3.56E-03 1.53E-03 2.16E-03 3.37E-03 4.98E-03 6.17E-030.15 2.26E-03 7.77E-04 1.20E-03 2.10E-03 3.33E-03 4.31E-030.3 8.86E-04 1.82E-04 3.28E-04 7.34E-04 1.44E-03 2.13E-030.5 3.51 E-04 4.63E-05 8.85E-05 2.39E-04 6.09E-04 1.04E-030.75 1.41 E-04 1.21 E-05 2.46E-05 7.66E-05 2.42E-04 4.90E-041. 6.71E-05 3.90E-06 8.47E-06 3.09E-05 1.11E-04 2.53E-041.5 2.1OE-05 6.OOE-07 1.49E-06 7.66E-06 3.23E-05 8.35E-053. 2.09E-06 1.77E-08 6.73E-08 5.66E-07 3.09E-06 8.12E-065. 3.05E-07 1.46E-09 8.23E-09 6.54E-08 4.77E-07 1.27E-067.5 6.02E-08 2.84E-10 1.29E-09 1.11E-08 9.37E-08 2.68E-0710. 1.87E-08 1.42E-10 3.47E-10 3.01E-09 2.76E-08 8.47E-08
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-le. Mean andFractile Seismic Hazard Curves for 2.5 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 5.05E-02 4.19E-02 4.50E-02 5.05E-02 5.58E-02 5.91E-020.001 4.76E-02 3.68E-02 4.13E-02 4.77E-02 5.35E-02 5.75E-020.005 2.95E-02 1.60E-02 2.04E-02 2.92E-02 3.90E-02 4.43E-020.01 1.95E-02 8.85E-03 1.20E-02 1.87E-02 2.72E-02 3.23E-020.015 1.43E-02 5.91E-03 8.12E-03 1.36E-02 2.04E-02 2.53E-020.03 7.49E-03 2.64E-03 3.84E-03 6.93E-03 1.11 E-02 1.42E-020.05 4.36E-03 1.31E-03 2.1OE-03 4.01E-03 6.64E-03 8.60E-030.075 2.79E-03 7.03E-04 1.23E-03 2.53E-03 4.31E-03 5.75E-030.1 2.01E-03 4.19E-04 7.89E-04 1.79E-03 3.23E-03 4.37E-030.15 1.23E-03 1.87E-04 3.84E-04 1.02E-03 2.07E-03 2.96E-030.3 4.36E-04 3.52E-05 8.OOE-05 2.84E-04 7.89E-04 1.38E-030.5 1.60E-04 8.12E-06 1.90E-05 7.55E-05 2.80E-04 6.OOE-040.75 6.03E-05 2.16E-06 5.20E-06 2.16E-05 9.51E-05 2.49E-041. 2.73E-05 7.77E-07 1.90E-06 8.23E-06 3.79E-05 1.13E-041.5 7.79E-06 1.55E-07 4.13E-07 1.90E-06 9.11E-06 3.05E-053. 6.43E-07 6.17E-09 2.07E-08 1.31 E-07 7.03E-07 2.19E-065. 8.57E-08 4.56E-10 1.64E-09 1.51 E-08 1.04E-07 3.19E-077.5 1.73E-08 1.40E-10 2.68E-10 2.39E-09 2.07E-08 7.23E-0810. 5.66E-09 1.08E-10 1.42E-10 6.36E-10 6.54E-09 2.49E-08
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-if. Mean and Fractile Seismic Hazard Curves for 1 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 3.82E-02 2.16E-02 2.80E-02 3.90E-02 4.83E-02 5.27E-020.001 2.92E-02 1.38E-02 1.87E-02 2.88E-02 3.95E-02 4.50E-020.005 1.05E-02 3.47E-03 5.27E-03 9.93E-03 1.55E-02 1.95E-020.01 5.96E-03 1.53E-03 2.60E-03 5.42E-03 9.24E-03 1.21 E-020.015 4.14E-03 8.47E-04 1.57E-03 3.68E-03 6.73E-03 8.98E-030.03 2.02E-03 2.25E-04 5.20E-04 1.67E-03 3.52E-03 5.12E-030.05 1.09E-03 6.45E-05 1.77E-04 8.OOE-04 2.01 E-03 3.09E-030.075 6.30E-04 2.01E-05 6.45E-05 4.07E-04 1.21 E-03 1.98E-030.1 4.12E-04 8.35E-06 2.88E-05 2.32E-04 8.12E-04 1.42E-030.15 2.15E-04 2.32E-06 8.60E-06 9.51E-05 4.19E-04 8.35E-040.3 5.87E-05 2.76E-07 1.10E-06 1.57E-05 1.01 E-04 2.64E-040.5 1.90E-05 6.64E-08 2.88E-07 3.52E-06 2.80E-05 8.85E-050.75 6.82E-06 2.22E-08 1.02E-07 1.04E-06 8.72E-06 3.14E-051. 3.07E-06 1.01E-08 4.83E-08 4.31E-07 3.63E-06 1.38E-051.5 8.99E-07 2.96E-09 1.49E-08 1.23E-07 1.01 E-06 3.90E-063. 8.93E-08 3.79E-10 1.62E-09 1.31 E-08 1.05E-07 3.95E-075. 1.57E-08 1.42E-10 3.19E-10 2.19E-09 1.84E-08 7.03E-087.5 4.08E-09 1.15E-10 1.44E-10 5.42E-10 4.37E-09 1.77E-0810. 1.56E-09 1.01E-10 1.32E-10 2.35E-10 1.60E-09 6.73E-09
 
==Attachment==
2 of Enclosure to Serial: RNP-RA/14-0118U.S. Nuclear Regulatory CommissionTable A-lg. Mean andFractile Seismic Hazard Curves for 0.5 Hz at RobinsonAMPS(g) MEAN 0.05 0.16 0.50 0.84 0.950.0005 2.14E-02 1.25E-02 1.60E-02 2.10E-02 2.68E-02 3.09E-020.001 1.40E-02 7.45E-03 9.93E-03 1.36E-02 1.79E-02 2.16E-020.005 4.81E-03 1.60E-03 2.53E-03 4.50E-03 7.13E-03 9.11E-030.01 2.72E-03 6.OOE-04 1.11E-03 2.35E-03 4.37E-03 6.00E-030.015 1.78E-03 2.84E-04 5.91 E-04 1.44E-03 2.96E-03 4.37E-030.03 7.00E-04 5.75E-05 1.49E-04 4.77E-04 1.23E-03 2.13E-030.05 2.99E-04 1.36E-05 4.01 E-05 1.57E-04 5.42E-04 1.08E-030.075 1.40E-04 3.90E-06 1.20E-05 5.66E-05 2.46E-04 5.66E-040.1 7.85E-05 1.55E-06 4.77E-06 2.46E-05 1.29E-04 3.42E-040.15 3.30E-05 3.84E-07 1.20E-06 6.93E-06 4.63E-05 1.53E-040.3 6.63E-06 2.76E-08 1.01 E-07 6.83E-07 6.26E-06 3.01E-050.5 1.85E-06 3.05E-09 1.38E-08 1.25E-07 1.31 E-06 7.55E-060.75 6.36E-07 5.12E-10 2.60E-09 3.23E-08 3.79E-07 2.39E-061. 2.89E-07 2.01E-10 8.12E-10 1.23E-08 1.60E-07 1.08E-061.5 9.15E-08 1.32E-10 2.1OE-10 3.01E-09 4.77E-08 3.42E-073. 1.15E-08 1.01 E-10 1.32E-10 3.09E-10 5.27E-09 4.37E-085. 2.25E-09 9.11E-11 1.0E-10 1.42E-10 9.79E-10 8.23E-097.5 5.70E-10 9.11E-11 1.01E-10 1.32E-10 2.92E-10 1.98E-0910. 2.04E-10 9.11E-11 1.01E-10 1.32E-10 1.67E-10 7.34E-10Above Tables were developed for H. B. Robinson Steam Electric Plant, Unit No. 2 reflectinginformation from the corrected version of the CEUS-SSC catalog.
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