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

Response to Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-Evaluations Related to Southeastern Catalog Changes

ML14325A645
Person / Time
Site:	Robinson
Issue date:	11/12/2014
From:	Glover R Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RNP-RA/14-0118, TAC MF3724, TAC MF3736, TAC MF3737, TAC MF3738
Download: ML14325A645 (23)

Text

R. Michael Glover H. B. Robinson Steam Electric Plant Unit 2

~ENERGY. Site Vice President Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0:843 857 1704 F: 843 857 1319 Mike. Glover@duke-energy.con November 12, 2014 Serial: RNP-RA/14-0118 10 CFR 50.54(f)

ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 I RENEWED LICENSE NO. DPR-23

Subject:

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)

References:

1. NRC Letter, Request for Information Pursuantto Title 10 of the Code of Federal Regulations 50.54() Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichiAccident, dated March 12, 2012, (ADAMS Accession No. ML12053A340)

2. NRC letter, Endorsement of EPRI Final Draft Report 1025287, "Seismic Evaluation Guidance," dated February 15, 2013 (ADAMS Accession Number ML12319A074)

3. EPRI Report 1025287, Seismic Evaluation Guidance: Screening, Prioritizationand Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic, dated February 2013 (ADAMS Accession Number ML12333A170)

4. NEI letter, Proposed Path Forwardfor NTTF Recommendation 2.1: Seismic Reevaluations, dated April 9, 2013 (ADAMS Accession Number ML13101A379)

5. NRC letter, Electric Power Research Institute Final Draft Report XXXXXX, "Seismic Evaluation Guidance: Augmented Approach for the Resolution of Fukushima 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 (ADAMS Accession Number ML13106A331)

6. NEI Letter, Seismic Evaluationsfor Plants in the Central and Eastern United States, dated March 12, 2014 (ADAMS Accession Nos. ML14083A584, ML14083A586 and ML14083A587)

7. Duke Energy letter to NRC, Seismic Hazard Evaluation, Response to NRC 10 CFR 50.54(f Request for Information Pursuantto Title 10 of the Code of FederalRegulations 50.54(o Regarding Recommendations 2.1, 2.3 and 9.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichiAccident, dated March 31, 2014 (ADAMS Accession No. ML14099A204)

8. NRC letter, Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Re-EvaluationsRelated Southeastern Catalogue Changes (TAC NOS. MF3724, MF 3736, MF3737, MF3738, and MF3831), dated October 23, 2014 (ADAMS Accession No. ML14268A516)

/'

Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Ladies and Gentlemen:

On March 12, 2012, the Nuclear Regulatory Commission (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 by 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 Reference

1. Section 4 of Reference 3 identified 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 part 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 the NRC by September 12, 2013, with the remaining seismic hazard and screening information submitted to the NRC by March 31, 2014. In Reference 5, the NRC agreed with this recommendation.

Reference 3 contains industry guidance and detailed information to be included in the Seismic Hazard 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 of Reference 3 in accordance with the schedule identified in Reference 4. As discussed in the Enclosure to the March 31, 2014, submittal letter (Reference 7), seismic hazard curves and a Ground Motion Response Spectrum (GMRS) were developed using current methodology. That GMRS was compared to the design basis Safe Shutdown Earthquake (SSE) response spectrum that was included in that submittal.

As discussed within Reference 1, NRC acknowledged that the current regulatory approach and the resultant plant capabilities provides reasonable confidence that an accident with consequences similar 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 public health and safety.

By letter dated March 12, 2014 (Reference 6), NEI provided the NRC with seismic core damage risk estimates based on updated seismic hazard information as it applies to operating nuclear reactors in the CEUS, which includes H. B. Robinson Steam Electric Plant, Unit No. 2. These risk assessments continue to support the conclusions of the NRC Generic Issue-1 99 "Safety/Risk Assessment" and indicate that current seismic design of operating reactors provide adequate protection and safety margin to withstand potential earthquakes that exceed the original design basis.

The Enclosure to this letter provides Duke Energy's response to the NRC's Request for Additional Information (RAI) (Reference 8) for H. B. Robinson, Unit No. 2.

This letter contains no new regulatory commitments.

Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission If 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 on AJ OVgV 4 c~r(9.21 Sincerely, R. Michael Glover Site Vice President RMG/shc

Enclosure:

Duke Energy Response to NRC RAI Regarding H. B. Robinson, Unit No. 2 cc: Ms. M. C. Barillas, NRC Project Manager, NRR Mr. K. M. Ellis, NRC Senior Resident Inspector Mr. V. M. McCree, NRC Region II Administrator

Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission ENCLOSURE DUKE ENERGY RESPONSE TO NRC REQUEST FOR ADDITIONAL INFORMATION H. B. ROBINSON, UNIT NO. 2

Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Review of Deviation from CEUS Seismic Source Characterization Cataloq Version 7.0 By letter dated March 12, 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12053A340), the NRC staff requested that licensees whose plants are located in the central and eastern United States (CEUS) use the recently published Central and Eastern United States Seismic Source Characterization for Nuclear Facilities (CEUS-SSC) to conduct the seismic hazard reevaluations. Specifically, Attachment 1 to "Seismic" Enclosure 1 of the March 12, 2012, letter stated that "regional and local refinements of the CEUS-SSC are not necessary for this evaluation." The staffs endorsement of the CEUS-SSC without refinement was intended to expedite the Near-Term Task Force (NTTF) 2.1 seismic hazard reevaluations and to ensure efficient use of NRC and licensee resources.

By letter dated February 15, 2013 (ADAMS Accession No. ML12319A074), "Endorsement of Electric Power Research Institute [EPRI] Final Draft Report 1025287, 'Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID),' the NRC staff endorsed using the SPID guidance.

Regarding the use of the CEUS-SSC for the NTTF Recommendation 2.1 seismic hazard reevaluations, Section 2 of the SPID states:

For site-specific licensing applications or site-specific safety decisions, these seismic sources would be reviewed on a site-specific basis to determine if they need to be updated. Such evaluations would be appropriate in a licensing application, where focus could be made on site-specific applications. However, for a screening-level study of multiple plants for the purpose of setting priorities, the use of these seismic sources as published is appropriate.

The CEUS-SSC was published as NUREG-2115, DOE/NE-0140, EPRI 1021097, "Central and Eastern United States Seismic Source Characterization for Nuclear Facilities," January 2012 (ADAMS Accession No. ML12048A776) and conducted using a Senior Seismic Hazard Analysis Committee (SSHAC) Level 3 study, consistent with NUREG/CR-6372, "Recommendations for Probabilistic Seismic Hazard Analysis: Guidance on Uncertainty and Use of Experts," April1997 (ADAMS Accession Nos. ML080090003 and ML080090004, respectively). The CEUS-SSC expert panel review considered the present state of knowledge of the Charleston seismic zone and known nontectonic events including reservoir-induced events in developing the seismic catalog for the CEUS-SSC. Section 6 of NUREG-2117, "Practical Implementation Guidelines for SSHAC Level 3 and 4 Hazard Studies: Rev. 1," Office of Nuclear Regulatory Research, 2012, (ADAMS Accession No. ML12118A445) recommends that viable regional probabilistic hazard studies, such as the CEUS-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 Energy Progress, Inc. and Duke Energy Carolinas, LLC, the licensees for H. B. Robinson Steam Electric Plant, Unit No. 2 (Robinson) and Oconee Nuclear Station, Units 1, 2, and 3 (Oconee); and South Carolina Electric and Gas Company, the licensee for Virgil C. Summer Nuclear Station, Unit 1 (VC Summer), submitted a revision to the CEUS-SSC catalog as part of the reevaluated seismic hazard submittal. Subsequently, by letter dated August 28, 2014 (ADAMS Accession No. ML14260A200),

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 South Carolina 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 seismic hazard reevaluations of H. B. Robinson, Oconee, and VC Summer plant sites.

Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Request for Additional Information Consistent with the 10 CFR 50.54(f) request for information and the SPID guidance, please provide a 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 the Recommendation 2.1 seismic hazard reevaluations of H.B. Robinson, Oconee, and VC Summer plant 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 catalog update, please describe the scope of the update and whether you also considered the impact of earthquakes 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 using both the currently-endorsed CEUS-SSC catalog as well as the proposed updated regional catalog used for the Recommendation 2.1 seismic hazard reevaluations of H.B. Robinson, Oconee, and VC Summer plant sites.

H. B. Robinson Response H. B. Robinson Steam Electric Plant, Unit No. 2 has decided not to provide a revised March 2014 seismic hazard reevaluation submittal reflecting the staff endorsed CEUS-SSC Catalog Version 7.0, but has instead opted to provide the proposed alternative as provided by the NRC Request for Additional 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, the RAI does not address the expectations communicated in the NRC endorsement letter to the industry dated February 15, 2013 (ADAMS Accession No. ML12319A074), "Endorsement of Electric Power Research Institute [EPRI] Final Draft Report 1025287, 'Seismic Evaluation Guidance: Screening, Prioritization and Implementation Details (SPID),' in which the NRC staff stated:

If a significant earthquake in the CEUS were to occur or new information were to emerge during the reevaluation period that could require an update of the CEUS-SSC model, the staff expects licensees to evaluate the significance of the new information to determine if the 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) that exceeds the review already performed. H. B. Robinson Steam Electric Plant, Unit No. 2 will credit the SSHAC Level 2 Study of the updated Regional CEUS-SSC Catalog. Duke Energy expects the results 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 by an EPRI letter dated August 28, 2014 (ADAMS Accession No. ML14260A209). The scope of the update of the catalog was performed with regard to two issues: (1) identification of additional reservoir induced seismicity (RIS) earthquakes in the southeastern US and (2) locations of earthquakes 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 as performed in EPRI 1021097 including Magnitude evaluations, de-clustering, and completeness calculations. This limited scope update was completed without including the impact of earthquakes in the region since the time period covered by the CEUS-SSC Catalog.

Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Attachments 1 and 2 to the Enclosure provide, in table form, control point seismic hazard curves developed using both the currently-endorsed CEUS-SSC catalog as well as the proposed updated regional catalog used for the Recommendation 2.1 seismic hazard reevaluation for H. B. Robinson Steam Electric Plant, Unit No. 2.

Therefore, Duke Energy has determined that the best approach for H. B. Robinson Steam Electric Plant, Unit No. 2 is to continue development of seismic hazard and GMRS using measured shear wave velocity and the latest Industry information and guidance. Results of the effort described during 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 by the CEUS-SSC Catalog will be performed as part of our Recommendation 2.1 site specific seismic hazard effort.

of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission (8 pages including this cover)

ATTACHMENT 1 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SEISMIC HAZARD CURVES IN TABLE FORMAT FROM THE CURRENTLY ENDORSED CEUS-SSC CATALOG of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Seismic Hazard Curves in Table Format using CEUS-SSC Catalog, Version 7.0 Table A-la. Mean and Fractile Seismic Hazard Curves for PGA at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.12E-02 3.84E-02 4.50E-02 5.20E-02 5.75E-02 6.09E-02 0.001 4.67E-02 3.09E-02 4.01 E-02 4.77E-02 5.35E-02 5.75E-02 0.005 2.63E-02 1.34E-02 1.98E-02 2.60E-02 3.33E-02 3.90E-02 0.01 1.71 E-02 8.47E-03 1.18E-02 1.64E-02 2.19E-02 2.88E-02 0.015 1.27E-02 6.17E-03 8.35E-03 1.20E-02 1.62E-02 2.32E-02 0.03 6.95E-03 3.09E-03 4.19E-03 6.36E-03 9.11E-03 1.40E-02 0.05 .4.19E-03 1.53E-03 2.22E-03 3.73E-03 5.83E-03 9.11E-03 0.075 2.67E-03 7.55E-04 1.20E-03 2.25E-03 4.01 E-03 6.26E-03 0.1 1.87E-03 4.13E-04 6.93E-04 1.49E-03 2.96E-03 4.77E-03 0.15 1.03E-03 1.60E-04 2.80E-04 7.03E-04 1.77E-03 3.05E-03 0.3 2.72E-04 2.13E-05 4.25E-05 1.29E-04 4.63E-04 1.02E-03 0.5 7.88E-05 3.01E-06 7.55E-06 3.19E-05 1.18E-04 3.09E-04 0.75 2.51 E-05 5.42E-07 1.69E-06 9.51 E-06 3.68E-05 9.51 E-05

1. 1.02E-05 1.57E-07 6.09E-07 3.68E-06 1.57E-05 3.73E-05 1.5 2.58E-06 2.76E-08 1.34E-07 8.35E-07 4.25E-06 9.93E-06

3. 2.09E-07 9.11E-10 4.98E-09 5.12E-08 3.42E-07 8.98E-07

5. 3.13E-08 1.42E-10 3.68E-10 5.35E-09 4.50E-08 1.38E-07 7.5 6.48E-09 1.04E-10 1.42E-10 8.23E-10 7.89E-09 2.92E-08

10. 1.98E-09 1.01E-10 1.32E-10 2.64E-10 2.1OE-09 9.11E-09 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-i b. Mean and Fractile Seismic Hazard Curves for 25 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.23E-02 4.13E-02 4.70E-02 5.27E-02 5.83E-02 6.17E-02 0.001 4.90E-02 3.57E-02 4.31 E-02 4.98E-02 5.50E-02 5.91 E-02 0.005 3.15E-02 1.84E-02 2.53E-02 3.14E-02 3.79E-02 4.43E-02 0.01 2.25E-02 1.23E-02 1.69E-02 2.19E-02 2.76E-02 3.52E-02 0.015 1.77E-02 9.51E-03 1.29E-02 1.69E-02 2.19E-02 2.96E-02 0.03 1.08E-02 5.58E-03 7.34E-03 1.02E-02 1.36E-02 1.95E-02 0.05 6.96E-03 3.23E-03 4.37E-03 6.45E-03 9.24E-03 1.31 E-02 0.075 4.64E-03 1.84E-03 2.64E-03 4.25E-03 6.45E-03 9.11 E-03 0.1 3.37E-03 1.13E-03 1.72E-03 3.01E-03 4.90E-03 6.93E-03 0.15 2.04E-03 4.77E-04 8.12E-04 1.72E-03 3.23E-03 4.70E-03 0.3 7.09E-04 6.83E-05 1.44E-04 4.70E-04 1.25E-03 2.16E-03 0.5 2.72E-04 1.57E-05 3.52E-05 1.44E-04 4.83E-04 9.79E-04 0.75 1.11E-04 5.83E-06 1.29E-05 5.20E-05 1.84E-04 4.13E-04

1. 5.35E-05 2.88E-06 6.64E-06 2.32E-05 8.72E-05 1.98E-04 1.5 1.68E-05 9.65E-07 2.25E-06 6.73E-06 2.76E-05 6.09E-05

3. 1.69E-06 3.95E-08 1.42E-07 8.12E-07 3.05E-06 6.17E-06

5. 3.34E-07 1.46E-09 1.07E-08 1.27E-07 6.26E-07 1.38E-06 7.5 1.22E-07 1.69E-10 1.20E-09 1.95E-08 2.29E-07 5.91 E-07

10. 6.58E-08 1.32E-10 2.80E-10 4.50E-09 1.21E-07 3.42E-07 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-ic. Mean and Fractile Seismic Hazard Curves for 10 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.37E-02 4.50E-02 4.83E-02 5.35E-02 5.91 E-02 6.26E-02 0.001 5.16E-02 4.19E-02 4.63E-02 5.20E-02 5.66E-02 6.09E-02 0.005 3.62E-02 2.42E-02 2.96E-02 3.63E-02 4.25E-02 4.70E-02 0.01 2.62E-02 1.60E-02 2.01 E-02 2.60E-02 3.23E-02 3.68E-02 0.015 2.06E-02 1.18E-02 1.53E-02 2.01E-02 2.57E-02 3.05E-02 0.03 1.24E-02 6.73E-03 8.72E-03 1.20E-02 1.60E-02 2.01 E-02 0.05 8.02E-03 4.13E-03 5.35E-03 7.66E-03 1.05E-02 1.36E-02 0.075 5.45E-03 2.57E-03 3.47E-03 5.12E-03 7.34E-03 9.51E-03 0.1 4.05E-03 1.74E-03 2.42E-03 3.79E-03 5.58E-03 7.34E-03 0.15 2.57E-03 8.98E-04 1.34E-03 2.35E-03 3.79E-03 5.12E-03 0.3 9.90E-04 2.10E-04 3.57E-04 8.OOE-04 1.62E-03 2.46E-03 0.5 3.93E-04 5.20E-05 9.79E-05 2.64E-04 6.73E-04 1.18E-03 0.75 1.62E-04 1.34E-05 2.76E-05 9.24E-05 2.80E-04 5.50E-04

1. 7.93E-05 4.63E-06 1.04E-05 4.07E-05 1.36E-04 2.84E-04 1.5 2.59E-05 9.79E-07 2.49E-06 1.18E-05 4.37E-05 9.51E-05

3. 2.82E-06 7.77E-08 2.49E-07 1.01 E-06 4.83E-06 1.11E-05

5. 4.60E-07 8.47E-09 2.92E-08 1.53E-07 8.OOE-07 1.90E-06 7.5 1.06E-07 8.60E-10 4.01E-09 3.47E-08 1.84E-07 4.50E-07

10. 3.88E-08 2.04E-10 9.51E-10 1.15E-08 6.45E-08 1.72E-07 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-id. Mean and Fractile Seismic Hazard Curves for 5 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.41E-02 4.50E-02 4.90E-02 5.42E-02 5.91E-02 6.26E-02 0.001 5.27E-02 4.31E-02 4.77E-02 5.27E-02 5.83E-02 6.17E-02 0.005 3.93E-02 2.68E-02 3.19E-02 3.95E-02 4.63E-02 5.05E-02 0.01 2.89E-02 1.72E-02 2.19E-02 2.88E-02 3.57E-02 4.01E-02 0.015 2.26E-02 1.27E-02 1.67E-02 2.25E-02 2.88E-02 3.23E-02 0.03 1.32E-02 6.93E-03 9.24E-03 1.29E-02 1.72E-02 2.04E-02 0.05 8.16E-03 4.25E-03 5.58E-03 7.89E-03 1.08E-02 1.31 E-02 0.075 5.39E-03 2.64E-03 3.52E-03 5.12E-03 7.23E-03 8.85E-03 0.1 3.97E-03 1.79E-03 2.46E-03 3.79E-03 5.42E-03 6.73E-03 0.15 2.51E-03 9.37E-04 1.38E-03 2.35E-03 3.63E-03 4.63E-03 0.3 9.78E-04 2.32E-04 3.90E-04 8.23E-04 1.57E-03 2.29E-03 0.5 3.90E-04 6.09E-05 1.11E-04 2.76E-04 6.64E-04 1.11E-03 0.75 1.59E-04 1.62E-05 3.19E-05 9.37E-05 2.68E-04 5.27E-04

1. 7.70E-05 5.35E-06 1.13E-05 3.95E-05 1.29E-04 2.76E-04 1.5 2.49E-05 8.60E-07 2.1OE-06 1.07E-05 4.01E-05 9.37E-05

3. 2.72E-06 2.72E-08 1.08E-07 8.60E-07 4.43E-06 1.07E-05

5. 4.30E-07 2.22E-09 1.32E-08 1.04E-07 7.13E-07 1.84E-06 7.5 9.06E-08 3.68E-10 1.95E-09 1.77E-08 1.46E-07 4.13E-07

10. 2.91E-08 1.60E-10 4.83E-10 4.83E-09 4.43E-08 1.34E-07 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-le. Mean and Fractile Seismic Hazard Curves for 2.5 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.31E-02 4.37E-02 4.77E-02 5.35E-02 5.83E-02 6.17E-02 0.001 5.OOE-02 3.84E-02 4.37E-02 5.05E-02 5.66E-02 6.OOE-02 0.005 3.15E-02 1.72E-02 2.19E-02 3.09E-02 4.13E-02 4.63E-02 0.01 2.09E-02 9.79E-03 1.29E-02 2.01 E-02 2.92E-02 3.47E-02 0.015 1.54E-02 6.54E-03 8.85E-03 1.46E-02 2.19E-02 2.68E-02 0.03 8.15E-03 2.92E-03 4.25E-03 7.55E-03 1.21 E-02 1.53E-02 0.05 4.76E-03 1.49E-03 2.32E-03 4.37E-03 7.13E-03 9.37E-03 0.075 3.03E-03 8.OOE-04 1.36E-03 2.76E-03 4.70E-03 6.17E-03 0.1 2.18E-03 4.90E-04 8.85E-04 1.95E-03 3.47E-03 4.70E-03 0.15 1.32E-03 2.22E-04 4.37E-04 1.11E-03 2.22E-03 3.14E-03 0.3 4.68E-04 4.43E-05 9.51 E-05 3.14E-04 8.35E-04 1.44E-03 0.5 1.72E-04 1.07E-05 2.39E-05 8.72E-05 3.01E-04 6.26E-04 0.75 6.56E-05 2.96E-06 6.83E-06 2.64E-05 1.04E-04 2.60E-04

1. 3.01 E-05 1.08E-06 2.60E-06 1.04E-05 4.37E-05 1.20E-04 1.5 8.81E-06 2.22E-07 5.83E-07 2.60E-06 1.13E-05 3.37E-05

3. 7.91E-07 8.98E-09 3.14E-08 1.98E-07 1.01 E-06 2.80E-06

5. 1.17E-07 6.17E-10 2.57E-09 2.35E-08 1.60E-07 4.70E-07 7.5 2.54E-08 1.53E-10 3.57E-10 3.73E-09 3.42E-08 1.13E-07

10. 8.66E-09 1.23E-10 1.55E-10 9.79E-10 1.07E-08 4.01E-08 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-If. Mean and Fractile Seismic Hazard Curves for 1 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 4.04E-02 2.32E-02 2.96E-02 4.13E-02 5.05E-02 5.50E-02 0.001 3.1OE-02 1.49E-02 2.01E-02 3.09E-02 4.19E-02 4.77E-02 0.005 1.12E-02 3.73E-03 5.66E-03 1.05E-02 1.67E-02 2.07E-02 0.01 6.33E-03 1.67E-03 2.76E-03 5.83E-03 9.79E-03 1.27E-02 0.015 4.38E-03 9.11E-04 1.67E-03 3.90E-03 7.03E-03 9.51E-03 0.03 2.12E-03 2.46E-04 5.50E-04 1.74E-03 3.68E-03 5.35E-03 0.05 1.14E-03 7.23E-05 1.92E-04 8.47E-04 2.10E-03 3.23E-03 0.075 6.58E-04 2.35E-05 7.03E-05 4.31E-04 1.27E-03 2.07E-03 0.1 4.30E-04 1.01 E-05 3.23E-05 2.46E-04 8.35E-04 1.49E-03 0.15 2.25E-04 2.96E-06 1.02E-05 1.04E-04 4.37E-04 8.72E-04 0.3 6.20E-05 3.90E-07 1.49E-06 1.79E-05 1.07E-04 2.76E-04 0.5 2.03E-05 9.79E-08 4.19E-07 4.37E-06 3.05E-05 9.24E-05 0.75 7.44E-06 3.37E-08 1.55E-07 1.36E-06 9.93E-06 3.37E-05

1. 3.41 E-06 1.57E-08 7.23E-08 5.91 E-07 4.31 E-06 1.51 E-05 1.5 1.04E-06 4.77E-09 2.32E-08 1.79E-07 1.27E-06 4.50E-06

3. 1.15E-07 5.20E-10 2.53E-09 2.01E-08 1.46E-07 5.12E-07

5. 2.21E-08 1.57E-10 4.37E-10 3.33E-09 2.72E-08 1.01 E-07 7.5 6.OOE-09 1.32E-10 1.62E-10 7.89E-10 6.64E-09 2.68E-08

10. 2.34E-09 1.01E-10 1.32E-10 3.09E-10 2.39E-09 1.02E-08 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-lg. Mean and Fractile Seismic Hazard Curves for 0.5 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 2.28E-02 1.34E-02 1.72E-02 2.25E-02 2.84E-02 3.33E-02 0.001 1.48E-02 8.OOE-03 1.05E-02 1.44E-02 1.90E-02 2.32E-02 0.005 5.01 E-03 1.72E-03 2.68E-03 4.63E-03 7.34E-03 9.37E-03 0.01 2.81E-03 6.45E-04 1.16E-03 2.46E-03 4.50E-03 6.17E-03 0.015 1.83E-03 3.09E-04 6.26E-04 1.49E-03 3.05E-03 4.50E-03 0.03 7.19E-04 6.36E-05 1.57E-04 4.90E-04 1.27E-03 2.16E-03 0.05 3.08E-04 1.60E-05 4.31E-05 1.67E-04 5.58E-04 1.10E-03 0.075 1.45E-04 4.77E-06 1.34E-05 5.91 E-05 2.53E-04 5.83E-04 0.1 8.13E-05 1.92E-06 5.50E-06 2.64E-05 1.34E-04 3.52E-04 0.15 3.44E-05 4.98E-07 1.49E-06 7.77E-06 4.90E-05 1.60E-04 0.3 7.08E-06 3.73E-08 1.34E-07 8.60E-07 7.13E-06 3.19E-05 0.5 2.03E-06 4.25E-09 1.95E-08 1.72E-07 1.62E-06 8.47E-06 0.75 7.21E-07 7.13E-10 3.73E-09 4.63E-08 5.05E-07 2.96E-06

1. 3.37E-07 2.42E-10 1.16E-09 1.79E-08 2.22E-07 1.38E-06 1.5 1.12E-07 1.32E-10 2.64E-10 4.50E-09 6.83E-08 4.56E-07

3. 1.53E-08 1.01E-10 1.32E-10 4.37E-10 8.12E-09 6.17E-08

5. 3.19E-09 9.11E-11 1.04E-10 1.51E-10 1.44E-09 1.20E-08 7.5 8.38E-10 9.11E-11 1.01E-10 1.32E-10 3.95E-10 2.88E-09

10. 3.06E-10 9.11E-11 1.01E-10 1.32E-10 1.98E-10 1.05E-09 Above Tables were developed for H. B. Robinson Steam Electric Plant, Unit No. 2 reflecting information from the staff endorsed CEUS-SSC Catalog Version 7.0 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission (8 pages including this cover)

ATTACHMENT 2 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 SEISMIC HAZARD CURVES IN TABLE FORMAT USING CORRECTED REGIONAL CEUS-SSC CATALOG FOR THE RECOMMENDATION 2.1 SEISMIC HAZARD REEVALUATION of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Seismic Hazard Curves in Table Format using Corrected Regional CEUS-SSC Catalog for the Recommendation 2.1 Seismic Hazard Reevaluation Table A-la. Mean and Fractile Seismic Hazard Curves for PGA at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 4.87E-02 3.68E-02 4.31 E-02 4.90E-02 5.50E-02 5.83E-02 0.001 4.43E-02 2.92E-02 3.79E-02 4.50E-02 5.12E-02 5.50E-02 0.005 2.44E-02 1.21 E-02 1.82E-02 2.42E-02 3.09E-02 3.68E-02 0.01 1.56E-02 7.55E-03 1.07E-02 1.51 E-02 2.01E-02 2.68E-02 0.015 1.15E-02 5.42E-03 7.45E-03 1.08E-02 1.46E-02 2.13E-02 0.03 6.20E-03 2.64E-03 3.68E-03 5.66E-03 8.12E-03 1.29E-02 0.05 3.72E-03 1.29E-03 1.92E-03 3.28E-03 5.27E-03 8.12E-03 0.075 2.38E-03 6.09E-04 1.02E-03 2.01 E-03 3.63E-03 5.66E-03 0.1 1.66E-03 3.28E-04 5.83E-04 1.31 E-03 2.68E-03 4.31E-03 0.15 9.09E-04 1.20E-04 2.22E-04 6.09E-04 1.60E-03 2.76E-03 0.3 2.33E-04 1.42E-05 2.96E-05 9.93E-05 4.01 E-04 9.24E-04 0.5 6.44E-05 1.95E-06 4.98E-06 2.13E-05 9.24E-05 2.68E-04 0.75 1.94E-05 3.33E-07 1.07E-06 6.17E-06 2.60E-05 7.45E-05

1. 7.51 E-06 9.93E-08 3.68E-07 2.32E-06 1.04E-05 2.80E-05 1.5 1.76E-06 1.82E-08 8.12E-08 5.05E-07 2.64E-06 6.73E-06

3. 1.29E-07 6.73E-10 3.28E-09 3.05E-08 2.07E-07 5.50E-07

5. 1.90E-08 1.32E-10 2.84E-10 3.19E-09 2.64E-08 8.35E-08 7.5 3.92E-09 1.01E-10 1.32E-10 5.27E-10 4.63E-09 1.77E-08

10. 1.19E-09 9.37E-11 1.23E-10 2.01E-10 1.32E-09 5.58E-09 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-I b. Mean and Fractile Seismic Hazard Curves for 25 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 4.98E-02 3.95E-02 4.43E-02 5.05E-02 5.50E-02 5.83E-02 0.001 4.65E-02 3.42E-02 4.07E-02 4.70E-02 5.27E-02 5.58E-02 0.005 2.94E-02 1.69E-02 2.32E-02 2.92E-02 3.57E-02 4.13E-02 0.01 2.07E-02 1.13E-02 1.53E-02 2.01E-02 2.53E-02 3.28E-02 0.015 1.62E-02 8.47E-03 1.16E-02 1.55E-02 1.98E-02 2.76E-02 0.03 9.73E-03 4.83E-03 6.54E-03 9.11E-03 1.23E-02 1.79E-02 0.05 6.19E-03 2.80E-03 3.79E-03 5.75E-03 8.23E-03 1.18E-02 0.075 4.11E-03 1.55E-03 2.25E-03 3.73E-03 5.75E-03 8.12E-03 0.1 2.98E-03 9.24E-04 1.46E-03 2.68E-03 4.37E-03 6.26E-03 0.15 1.80E-03 3.84E-04 6.73E-04 1.51 E-03 2.88E-03 4.25E-03 0.3 6.20E-04 5.05E-05 1.11E-04 3.95E-04 1.11E-03 1.98E-03 0.5 2.33E-04 1.02E-05 2.46E-05 1.13E-04 4.13E-04 8.72E-04 0.75 9.18E-05 3.63E-06 8.47E-06 3.73E-05 1.51 E-04 3.63E-04

1. 4.30E-05 1.87E-06 4.13E-06 1.57E-05 6.64E-05 1.67E-04 1.5 1.27E-05 6.09E-07 1.38E-06 4.50E-06 1.95E-05 4.70E-05

3. 1.13E-06 2.60E-08 8.60E-08 4.77E-07 1.95E-06 4.13E-06

5. 2.1OE-07 1.05E-09 6.45E-09 7.55E-08 3.95E-07 8.47E-07 7.5 7.50E-08 1.53E-10 7.55E-10 1.21E-08 1.32E-07 3.57E-07

10. 4.03E-08 1.32E-10 2.13E-10 2.84E-09 6.93E-08 2.07E-07 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-ic. Mean and Fractile Seismic Hazard Curves for 10 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.11E-02 4.25E-02 4.56E-02 5.12E-02 5.66E-02 5.91E-02 0.001 4.91E-02 4.01E-02 4.37E-02 4.90E-02 5.42E-02 5.75E-02 0.005 3.40E-02 2.29E-02 2.76E-02 3.42E-02 4.01 E-02 4.43E-02 0.01 2.43E-02 1.46E-02 1.84E-02 2.42E-02 3.01 E-02 3.47E-02 0.015 1.89E-02 1.08E-02 1.38E-02 1.87E-02 2.35E-02 2.84E-02 0.03 1.13E-02 6.OOE-03 7.77E-03 1.08E-02 1.44E-02 1.84E-02 0.05 7.18E-03 3.57E-03 4.77E-03 6.83E-03 9.37E-03 1.21E-02 0.075 4.85E-03 2.19E-03 3.01E-03 4.56E-03 6.54E-03 8.60E-03 0.1 3.61E-03 1.46E-03 2.1OE-03 3.37E-03 5.05E-03 6.64E-03 0.15 2.29E-03 7.34E-04 1.15E-03 2.07E-03 3.42E-03 4.63E-03 0.3 8.80E-04 1.64E-04 2.96E-04 6.93E-04 1.46E-03 2.25E-03 0.5 3.44E-04 3.90E-05 7.55E-05 2.22E-04 6.OOE-04 1.08E-03 0.75 1.38E-04 9.51E-06 2.04E-05 7.23E-05 2.42E-04 4.90E-04

1. 6.63E-05 3.14E-06 7.23E-06 3.05E-05 1.11E-04 2.49E-04 1.5 2.06E-05 6.45E-07 1.62E-06 8.12E-06 3.33E-05 7.89E-05

3. 2.01 E-06 4.98E-08 1.51 E-07 6.54E-07 3.28E-06 8.OOE-06

5. 3.02E-07 5.66E-09 1.84E-08 9.51E-08 5.12E-07 1.23E-06 7.5 6.66E-08 6.OOE-10 2.46E-09 2.07E-08 1.15E-07 2.76E-07

10. 2.39E-08 1.74E-10 6.09E-10 6.93E-09 4.07E-08 1.05E-07 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-id. Mean and Fractile Seismic Hazard Curves for 5 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.15E-02 4.31E-02 4.63E-02 5.20E-02 5.66E-02 6.00E-02 0.001 5.02E-02 4.13E-02 4.50E-02 5.05E-02 5.50E-02 5.83E-02 0.005 3.70E-02 2.49E-02 2.96E-02 3.73E-02 4.43E-02 4.83E-02 0.01 2.70E-02 1.60E-02 2.04E-02 2.68E-02 3.37E-02 3.73E-02 0.015 2.10E-02 1.16E-02 1.53E-02 2.07E-02 2.68E-02 3.05E-02 0.03 1.20E-02 6.26E-03 8.35E-03 1.16E-02 1.57E-02 1.87E-02 0.05 7.36E-03 3.73E-03 4.98E-03 7.13E-03 9.79E-03 1.20E-02 0.075 4.85E-03 2.29E-03 3.09E-03 4.63E-03 6.54E-03 8.12E-03 0.1 3.56E-03 1.53E-03 2.16E-03 3.37E-03 4.98E-03 6.17E-03 0.15 2.26E-03 7.77E-04 1.20E-03 2.10E-03 3.33E-03 4.31E-03 0.3 8.86E-04 1.82E-04 3.28E-04 7.34E-04 1.44E-03 2.13E-03 0.5 3.51 E-04 4.63E-05 8.85E-05 2.39E-04 6.09E-04 1.04E-03 0.75 1.41 E-04 1.21 E-05 2.46E-05 7.66E-05 2.42E-04 4.90E-04

1. 6.71E-05 3.90E-06 8.47E-06 3.09E-05 1.11E-04 2.53E-04 1.5 2.1OE-05 6.OOE-07 1.49E-06 7.66E-06 3.23E-05 8.35E-05

3. 2.09E-06 1.77E-08 6.73E-08 5.66E-07 3.09E-06 8.12E-06

5. 3.05E-07 1.46E-09 8.23E-09 6.54E-08 4.77E-07 1.27E-06 7.5 6.02E-08 2.84E-10 1.29E-09 1.11E-08 9.37E-08 2.68E-07

10. 1.87E-08 1.42E-10 3.47E-10 3.01E-09 2.76E-08 8.47E-08 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-le. Mean and Fractile Seismic Hazard Curves for 2.5 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 5.05E-02 4.19E-02 4.50E-02 5.05E-02 5.58E-02 5.91E-02 0.001 4.76E-02 3.68E-02 4.13E-02 4.77E-02 5.35E-02 5.75E-02 0.005 2.95E-02 1.60E-02 2.04E-02 2.92E-02 3.90E-02 4.43E-02 0.01 1.95E-02 8.85E-03 1.20E-02 1.87E-02 2.72E-02 3.23E-02 0.015 1.43E-02 5.91E-03 8.12E-03 1.36E-02 2.04E-02 2.53E-02 0.03 7.49E-03 2.64E-03 3.84E-03 6.93E-03 1.11 E-02 1.42E-02 0.05 4.36E-03 1.31E-03 2.1OE-03 4.01E-03 6.64E-03 8.60E-03 0.075 2.79E-03 7.03E-04 1.23E-03 2.53E-03 4.31E-03 5.75E-03 0.1 2.01E-03 4.19E-04 7.89E-04 1.79E-03 3.23E-03 4.37E-03 0.15 1.23E-03 1.87E-04 3.84E-04 1.02E-03 2.07E-03 2.96E-03 0.3 4.36E-04 3.52E-05 8.OOE-05 2.84E-04 7.89E-04 1.38E-03 0.5 1.60E-04 8.12E-06 1.90E-05 7.55E-05 2.80E-04 6.OOE-04 0.75 6.03E-05 2.16E-06 5.20E-06 2.16E-05 9.51E-05 2.49E-04

1. 2.73E-05 7.77E-07 1.90E-06 8.23E-06 3.79E-05 1.13E-04 1.5 7.79E-06 1.55E-07 4.13E-07 1.90E-06 9.11E-06 3.05E-05

3. 6.43E-07 6.17E-09 2.07E-08 1.31 E-07 7.03E-07 2.19E-06

5. 8.57E-08 4.56E-10 1.64E-09 1.51 E-08 1.04E-07 3.19E-07 7.5 1.73E-08 1.40E-10 2.68E-10 2.39E-09 2.07E-08 7.23E-08

10. 5.66E-09 1.08E-10 1.42E-10 6.36E-10 6.54E-09 2.49E-08 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-if. Mean and Fractile Seismic Hazard Curves for 1 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 3.82E-02 2.16E-02 2.80E-02 3.90E-02 4.83E-02 5.27E-02 0.001 2.92E-02 1.38E-02 1.87E-02 2.88E-02 3.95E-02 4.50E-02 0.005 1.05E-02 3.47E-03 5.27E-03 9.93E-03 1.55E-02 1.95E-02 0.01 5.96E-03 1.53E-03 2.60E-03 5.42E-03 9.24E-03 1.21 E-02 0.015 4.14E-03 8.47E-04 1.57E-03 3.68E-03 6.73E-03 8.98E-03 0.03 2.02E-03 2.25E-04 5.20E-04 1.67E-03 3.52E-03 5.12E-03 0.05 1.09E-03 6.45E-05 1.77E-04 8.OOE-04 2.01 E-03 3.09E-03 0.075 6.30E-04 2.01E-05 6.45E-05 4.07E-04 1.21 E-03 1.98E-03 0.1 4.12E-04 8.35E-06 2.88E-05 2.32E-04 8.12E-04 1.42E-03 0.15 2.15E-04 2.32E-06 8.60E-06 9.51E-05 4.19E-04 8.35E-04 0.3 5.87E-05 2.76E-07 1.10E-06 1.57E-05 1.01 E-04 2.64E-04 0.5 1.90E-05 6.64E-08 2.88E-07 3.52E-06 2.80E-05 8.85E-05 0.75 6.82E-06 2.22E-08 1.02E-07 1.04E-06 8.72E-06 3.14E-05

1. 3.07E-06 1.01E-08 4.83E-08 4.31E-07 3.63E-06 1.38E-05 1.5 8.99E-07 2.96E-09 1.49E-08 1.23E-07 1.01 E-06 3.90E-06

3. 8.93E-08 3.79E-10 1.62E-09 1.31 E-08 1.05E-07 3.95E-07

5. 1.57E-08 1.42E-10 3.19E-10 2.19E-09 1.84E-08 7.03E-08 7.5 4.08E-09 1.15E-10 1.44E-10 5.42E-10 4.37E-09 1.77E-08

10. 1.56E-09 1.01E-10 1.32E-10 2.35E-10 1.60E-09 6.73E-09 of Enclosure to Serial: RNP-RA/14-0118 U.S. Nuclear Regulatory Commission Table A-lg. Mean and Fractile Seismic Hazard Curves for 0.5 Hz at Robinson AMPS(g) MEAN 0.05 0.16 0.50 0.84 0.95 0.0005 2.14E-02 1.25E-02 1.60E-02 2.10E-02 2.68E-02 3.09E-02 0.001 1.40E-02 7.45E-03 9.93E-03 1.36E-02 1.79E-02 2.16E-02 0.005 4.81E-03 1.60E-03 2.53E-03 4.50E-03 7.13E-03 9.11E-03 0.01 2.72E-03 6.OOE-04 1.11E-03 2.35E-03 4.37E-03 6.00E-03 0.015 1.78E-03 2.84E-04 5.91 E-04 1.44E-03 2.96E-03 4.37E-03 0.03 7.00E-04 5.75E-05 1.49E-04 4.77E-04 1.23E-03 2.13E-03 0.05 2.99E-04 1.36E-05 4.01 E-05 1.57E-04 5.42E-04 1.08E-03 0.075 1.40E-04 3.90E-06 1.20E-05 5.66E-05 2.46E-04 5.66E-04 0.1 7.85E-05 1.55E-06 4.77E-06 2.46E-05 1.29E-04 3.42E-04 0.15 3.30E-05 3.84E-07 1.20E-06 6.93E-06 4.63E-05 1.53E-04 0.3 6.63E-06 2.76E-08 1.01 E-07 6.83E-07 6.26E-06 3.01E-05 0.5 1.85E-06 3.05E-09 1.38E-08 1.25E-07 1.31 E-06 7.55E-06 0.75 6.36E-07 5.12E-10 2.60E-09 3.23E-08 3.79E-07 2.39E-06

1. 2.89E-07 2.01E-10 8.12E-10 1.23E-08 1.60E-07 1.08E-06 1.5 9.15E-08 1.32E-10 2.1OE-10 3.01E-09 4.77E-08 3.42E-07

3. 1.15E-08 1.01 E-10 1.32E-10 3.09E-10 5.27E-09 4.37E-08

5. 2.25E-09 9.11E-11 1.0E-10 1.42E-10 9.79E-10 8.23E-09 7.5 5.70E-10 9.11E-11 1.01E-10 1.32E-10 2.92E-10 1.98E-09

10. 2.04E-10 9.11E-11 1.01E-10 1.32E-10 1.67E-10 7.34E-10 Above Tables were developed for H. B. Robinson Steam Electric Plant, Unit No. 2 reflecting information from the corrected version of the CEUS-SSC catalog.