ML18025B737: Difference between revisions

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| number = ML18025B737
| number = ML18025B737
| issue date = 02/05/2018
| issue date = 02/05/2018
| title = 01/18/2018 Summary of Meeting with Nuclear Energy Institute to Discuss Alternate Methods to Account for Seismic Risk in 10 CFR 50.69 Applications Without Use of Seismic Probabilistic Risk Assessment
| title = Summary of Meeting with Nuclear Energy Institute to Discuss Alternate Methods to Account for Seismic Risk in 10 CFR 50.69 Applications Without Use of Seismic Probabilistic Risk Assessment
| author name = Miller G
| author name = Miller G
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV

Latest revision as of 15:56, 2 December 2019

Summary of Meeting with Nuclear Energy Institute to Discuss Alternate Methods to Account for Seismic Risk in 10 CFR 50.69 Applications Without Use of Seismic Probabilistic Risk Assessment
ML18025B737
Person / Time
Issue date: 02/05/2018
From: Geoffrey Miller
Plant Licensing Branch IV
To: Markley M
Plant Licensing Branch II
Miller G
References
Download: ML18025B737 (6)


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 February 5, 2018 MEMORANDUM TO: Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation FROM: G. Edward Miller, Project Manager Special Projects and Process Branch bv~

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Office of Nuclear Reactor Regulation

SUBJECT:

SUMMARY

OF JANUARY 18, 2018, PUBLIC MEETING WITH NUCLEAR ENERGY INSTITUTE REGARDING 10 CFR 50.69 LICENSE AMENDMENT REQUESTS On January 18, 2018, a Category 2 public meeting 1 was held between representatives of the U.S. Nuclear Regulatory Commission (NRC), Nuclear Energy Institute (NEI), Electric Power Research Institute (EPRI), and other licensees. The purpose of the meeting was to discuss NEl's model license amendment request (LAR) to implement a risk-informed program for categorization and treatment of structures, systems, and components (SSCs) for nuclear power reactors in accordance with Section 50.69, "Risk-informed categorization and treatment of structures, systems, and components for nuclear power reactors," of Title 10 of the Code of Federal Regulations (10 CFR 50.69). This public meeting was a continuation of public meetings held on August 18, 2016, 2 and January 25, 3 June 21, 4 September 6, 5 and October 23, 2017, 6 on the same topic. The meeting focused on augmentations to the NEI template to address lessons learned from those submittals currently under review. Additionally, this meeting covered potential approaches to implementing 10 CFR 50.69 when a licensee did not have seismic probabilistic risk assessment (SPRA) or a seismic margins analysis.

The NRC staff presented slides7 regarding feedback and suggestions based on submittals currently under review. In summary, the slides provided the following feedback:

  • The LARs need to include a categorization process summary description;

The meeting notice and agenda are available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML17353A016.

2 The meeting summary for the August 18, 2016, meeting is available under ADAMS Accession No. ML16250A548.

3 The meeting summary for the January 25, 2017, meeting is available under ADAMS Accession No. ML17027A251.

4 The meeting summary for the June 21, 2017, meeting is available under ADAMS Accession No. ML17177A063.

5 The meeting summary for the September 6, 2017, public meeting is available under ADAMS Accession No. ML17265A020.

6 The meeting summary for the October 23, 2017, public meeting is available under ADAMS Accession No. ML17305A242.

7 The NRC slides are available under ADAMS Accession No. ML18017B141.

M. Markley

  • Deviations should be minimized;
  • Methods not accepted by NRC should be avoided ;
  • Consistency with NEI 00-04, Figure 5-6 (external events), should be demonstrated in the LAR;
  • Inclusion of Class 1 passive component in categorization would represent an expansion beyond previously accepted methods and would complicate review;
  • The NRC staff indicated that further evaluation of the impact of certain Westinghouse Nuclear Safety Advisory Letters (e.g., NSAL-00-006 8 ) on this topic may be needed: and
  • It was not clear that the rule would allow alternative treatment for Class 1 passive components beyond in-service testing.

Subsequently, NEI staff presented slides 9 that summarized changes to the template LAR that had been made based upon previous NRC staff feedback and lessons learned from in-house reviews. Additionally, NEI provided the current version of the template LAR. 10 Subsequently, NEI staff, supported by EPRI staff, presented slides 11 that analyzed the value of including seismic hazards in the categorization of SSCs for sites that had high seismic hazards and had performed SPRAs. The slides indicated that in the two examples, inclusion of the SPRA did not uniquely identify any SSCs with high safety significance (i.e., all SSCs identified by the SPRA were also identified as high safety significance by another model such as the fire PRA). A third example was provided which identified 5 components high safety significant that were not identified by another categorization process. The conclusion of the analysis asserted that explicit consideration of seismic risks in the categorization process was not necessary and proposed a 3-tiered approach for seismic categorization that they plan to finalize after a 4th plant model is completed. They indicated their intent to present these results at a subsequent public meeting.

The NRC staff indicated that such an approach to the seismic aspect of 10 CFR 50.69 applications may be feasible, but indicated that it would be a deviation from the currently endorsed guidance. Similar to the prior meeting on this topic, the NRC staff indicated that although not an exhaustive list, if such an approach was pursued, the following would need to be addressed:

  • Justification for how the studies presented can be generalized to be applicable for the remainder of the fleet
  • Justification of any changes needed to address the impact on the categorization process:

o Integrated importance assessment o Additional information that may need to be provided to the integrated decision-making panel

  • Specific entry conditions of usage for the analysis such as:

o Magnitude and spectrum of the site-specific seismic hazard o Containment type o Component limitations o Estimated seismic risk 8 NSAL-00-006 is available under ADAMS Accession No. ML091190189.

9 The NEI slides are available under ADAMS Accession No. ML18022A113.

10 The version of the template LAR provided is available under ADAMS Accession No. ML18022A112.

11 The NEI slides (prepared by EPRI) are available under ADAMS Accession No. ML18022A111.

M. Markley

  • Relevance of the Near Term Task Force (NTTF) 2.1 categorization process to differentiating between "medium" and "high" seismic sites The feedback provided by the NRC staff is not all-inclusive and it is possible that additional questions could arise during an actual review where this concept is applied.

No regulatory decisions were made and both the NRC staff and the NEI indicated that they would consider the items discussed in the meeting.

Following the discussion, an opportunity was afforded to any other participants who wished to ask questions or make comments. No questions or comments were received.

The list of attendees is enclosed to this summary.

Enclosure:

List of Attendees

ENCLOSURE LIST OF ATTENDEES

Public Meeting With NEI to Sign In Sheet Discuss 50.69 and Seismic DATE: Jan 18, 2018 Approaches Organization

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Public Meeting With NEI to Sign In Sheet Discuss 50.69 and Seismic DATE: Jan 18, 2018 Approaches

ML180258737 *via e-mail OFFICE NRR/DORL/LSPB/PM NRR/DORL/LSPB/LA NRR/DRA/APLA/BC NAME GEMiller JBurkhardt SRosenberg DATE 2/1/2018 1/29/18 2/1/2018 OFFICE NRR/DORL/LPL2-1 /BC NRR/DORL/LSPB/PM NAME MMarkley GEMiller DATE 2/5/2018 2/5/2018