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Category:Meeting Summary
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2023-08-17
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 7, 2014 LICENSEE: Indiana Michigan Power Company FACILITY: Donald C. Cook Nuclear Plant, Units 1 and 2
SUBJECT:
SUMMARY
OF THE JULY 9, 2014, CATEGORY 1 PUBLIC MEETING WITH INDIANA MICHIGAN POWER COMPANY TO DISCUSS SEISMIC HAZARD REEVALUATIONS ASSOCIATED WITH IMPLEMENTATION OF JAPAN LESSONS-LEARNED NEAR-TERM TASK FORCE RECOMMENDATION 2.1.
On July 9, 2014, the U.S. Nuclear Regulatory Commission (NRC or the staff) held a Category 1 public meeting 1 with Indiana Michigan Power Company (the licensee) for Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. The purpose of this meeting was to discuss issues resulting from the staff's screening and prioritization of CNP related to Enclosure 1, Recommendation 2.1: Seismic of the March 12, 2012, NRC request for information per Title 10 to the Code of Federal Regulations, Part 50, Section 50.54(f) lette~. By letter dated May 9, 2014, 3 the NRC staff categorized CNP, Units 1 and 2, as screened in to perform additional seismic evaluations, prioritization group 1 plant, with a risk evaluation due by June 17, 2017 based on the staff's screening review. By memo dated May 21, 2014, the NRC staff documented their preliminary Ground Motion Response Spectra (GMRS) curve in comparison to all licensee GMRS curves along with the plant's Safe Shutdown Earthquake (SSE) and Individual Plant Examination of External Events (IPEEE) High Confidence Low Probability of Failure (HCLPF) Spectra, also known as the IHS (IPEEE HCLPF Spectra). The public meeting supported an information exchange and understanding of engineering differences to achieve subsequent technical resolution.
To facilitate the discussion, the NRC staff and licensee representatives presented 4 the engineering details on the modeling inputs used to develop GMRS curves for CNP. The meeting highlights included:
- Licensee presented background on the development of shear wave velocity profiles from the CNP Preliminary Safety Analysis Report (PSAR) dated 1967. NRC staff asked for the licensee to provide the PSAR reference to support the ongoing review.
- NRC staff discussed whether the PSAR profiles continue to reflect more recent measurements of similar rock units.
- NRC staff agreed to licensee plans to proceed with a SSE scaling factor of 1.93 given that it should not impact interim action decisions.
1 The original meeting notice is available via the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML14182A182.
2 The 50.54(f) letter and Enclosure 1 are available under ADAMS Accession Nos. ML12053A340 and ML12056A047.
3 The May 9, 20141etter is available under ADAMS Accession No. ML14111A147.
4 The NRC and licensee slides can be found under ADAMS Accession Nos. ML14189A562 and ML14190A185.
- NRC staff discussed potential for an Request for Additional Information related to standard deviation applied of site response amplifications factors
- Licensee agreed that 25 ft. of beach sand should be included in Seismic Probabilistic Risk Assessment modeling for structures response modeling (e.g. containment)
In summary, the NRC staff stated that the primary differences between the NRC staff and licensee GMRS curves appear to result from:
- NRC staff unable to replicate licensee's GMRS because of differences in Amplification Factor as a function of input rock motion
- Approach in calculating Kappa
- Licensee considered sedimentary rock to have reference rock velocity for three of the six profiles rather than just one of three Finally, the NRC stated that a follow up request for additional information may be issued to document the licensee's technical basis and background information as well as any other clarifications associated with the information presented at the meeting.
No regulatory decisions or commitments were made during the meeting. The public was invited to observe the meeting and was given several opportunities to communicate with the NRC during the public meeting and before adjourning. The NRC staff received no public comments and no meeting feedback forms.
Please direct any inquiries to me at 301-415-2856, or Michaei.Balazik@nrc.gov.
~fjo eel M n ger Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
List of Attendees U.S. Nuclear Regulatory Commission Public Meeting with Indiana Michigan Power Company Concerning Seismic Hazard Reevaluation Submittals Japan Lessons-Learned Near-Term Task Force Recommendation 2.1: Seismic July 9, 2014 Name Organization Name Organization Jon Ake NRC/RES/DE Richard Rogalski Entergy Northwest Cliff Munson NRC/NRO/DSEA John Anderson AEP Stephanie Devlin NRC/NRO/DSEA Dan Ludwig Xcel Nuclear Nicholas DiFrancesco NRC/NRR/JLD John Richards EPRI Dogan Seber NRC/NRO/DSEA Justin Miller TVA Michael Balazik NRC/NRR/JLD David Ma Argonne National Lab John Ellegood NRC/RIII/DRP Brenda Kovarik Sargent and Lundy Juan Uribe NRC/NRR/JLD Jose Blanco Rizzo Associates Mike Franovich NRC/NRR/JLD Walt Silva Pacific Engineering Terry Beltz NRR/DORL Robin McGuire EPRI Zuhan Xi NRC/NRO Budd Maemer AEP Southern Nuclear Operating Andrea Kock NRC/NRO/DSEA Ronald Wittschen Company, Inc.
Quinton Lies AEP Ram Srinivasan Public Michael Scarpello AEP Jeff Kimball Rizzo Associates Michael Tschiltz NEI Joe Waters AEP Larry Weber AEP John Stegman AEP Michael Carlson AEP Jey Sekaran AEP Abbreviations:
AEP - American Electric Power DE - Division of Engineering DSEA - Division of Site Safety and Environmental Analysis DSRA - Division of Safety Systems & Risk Assessment EPRI- Electric Power Research Institute JLD - Japan Lessons-Learned Division NEI -Nuclear Energy Institute NRO- Office of New Reactors NRR- Office of Nuclear Reactor Regulation RES - Office of Nuclear Regulatory Research TVA- Tennessee Valley Authority Enclosure
- NRC staff discussed potential for an Request for Additional Information related to standard deviation applied of site response amplifications factors
- Licensee agreed that 25 ft. of beach sand should be included in Seismic Probabilistic Risk Assessment modeling for structures response modeling (e.g. containment)
In summary, the NRC staff stated that the primary differences between the NRC staff and licensee GMRS curves appear to result from:
- NRC staff unable to replicate licensee's GMRS because of differences in Amplification Factor as a function of input rock motion
- Approach in calculating Kappa
- Licensee considered sedimentary rock to have reference rock velocity for three of the six profiles rather than just one of three profiles Finally, the NRC stated that a follow up request for additional information may be issued to document the licensee's technical basis and background information as well as any other clarifications associated with the information presented at the meeting.
No regulatory decisions or commitments were made during the meeting. The public was invited to observe the meeting and was given several opportunities to communicate with the NRC during the public meeting and before adjourning. The NRC staff received no public comments and no meeting feedback forms.
Please direct any inquiries to me at 301-415-2856, or Michael. Balazik@nrc.gov.
IRA/
Michael Balazik, Project Manager Hazards Management Branch Japan Lessons-Learned Division Office of Nuclear Reactor Regulation Docket Nos. 50-315 and 50-316
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC DiFrancesco, NRR JLD R/F KManoly, NRR RidsNrrDorl Resource DJackson, NRO SWhaley, NRR RidsOpaMail RKaras, NRO Yli,NRR RidsOgcMaiiCenter CMuson, NRO JAke, RES RidsNroDsea RidsNroOd MJardaneh, NRO RidsOgcMaiiCenter RidsNrrLASLent RidsNrrDe RidsAcrsAcnw_MaiiCTR RidsRgn3MaiiCenter DPelton, NRR ADAMS Accession No ..* ML14209A942 OFFICE NRR/JLD/JHMB/PM NRR/JLD/LA NRR/JLD/JHMB/BC NRR/JLD/JHMB/PM NAME MBalazik SLent SWhaley MBalazik DATE 07/28/14 07/29/14 07/30/14 08/07/14 OFFICIAL RECORD COPY
