ML17333A077: Difference between revisions
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| issue date = 11/07/2017 | | issue date = 11/07/2017 | ||
| title = Infogram 14-1 November 7, 2017 Meeting | | title = Infogram 14-1 November 7, 2017 Meeting | ||
| author name = Benney B | | author name = Benney B, Kaizer J, Oesterle E, Sallman A | ||
| author affiliation = NRC/NRR/DLP | | author affiliation = NRC/NRR/DLP | ||
| addressee name = | | addressee name = | ||
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| docket = PROJ0694 | | docket = PROJ0694 | ||
| license number = | | license number = | ||
| contact person = Benney B | | contact person = Benney B | ||
| package number = ML17278A096 | | package number = ML17278A096 | ||
| document type = Slides and Viewgraphs | | document type = Slides and Viewgraphs | ||
Revision as of 14:46, 18 June 2019
| ML17333A077 | |
| Person / Time | |
|---|---|
| Site: | PROJ0694 |
| Issue date: | 11/07/2017 |
| From: | Brian Benney, Joshua Kaizer, Eric Oesterle, Ahsan Sallman Division of Licensing Projects |
| To: | |
| Benney B | |
| Shared Package | |
| ML17278A096 | List: |
| References | |
| Download: ML17333A077 (7) | |
Text
Infogram14-1 and Containment Analyses November 7, 2017 Brian Benney Ahsan Sallman Joshua KaizerEric Oesterle Objectives
- Discuss Infogram14-1 issue
- Discuss NRC response
- Discuss Industry response
- Discuss Future Activities
- Q &A Infogram14-1
- Infogramsare Westinghouse service oriented publications that discuss issues of interest to their customers*Infogram14-1 identified a potential non-conservatism in containment analysis
- Volumetric heat capacity for stainless steel (SS) used for reactor coolant system (RCS) metal not consistent with ASME code value
- Non-conservative results in post-accident containment pressures and temperatures NRC Response
- NRC learned of Infogram14-1 through interactions with stakeholders
- NRC responded by issuing requests for additional information on license amendment reviews that could be impacted by the issue
- Individual licensees responded by performing analyses to address the issue Industry Response
- Pressurizer Water Reactor Owners Group (PWROG) engaged NRC to pursue generic industry approach to address the issue
- Closed meetings were held between industry and NRC to review proprietary containment analysis codes used in analyses of record (AOR) by licensees
- Containment analysis codes used in AORs were demonstrated to include substantial conservatism to offset lower SS heat capacity factor -no safety issue
- PWROG proposed submitting a generic topical report (TR) to highlight conservatism in AORs that would address the issue and which licensees could adopt and include in their
licensing bases Current Status & Future Activities
- Based on results of licensees addressing this issue to date, NRC will no longer issue RAIs on license amendment requests that could be impacted by this
issue*Based on focused industry attention and ownership to resolve issue NRC believes that issue can be appropriately addressed through licensee corrective actions programs (i.e., inspection issue vs. licensing
issue)*PWROG is planning to submit a TR to highlight conservatism in AORs such that licensees can include TR in licensing basis and close out corrective action.
Infogram14-1Questions?