ML17333A077: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(StriderTol Bot change)
 
(2 intermediate revisions by the same user not shown)
Line 3: Line 3:
| 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 J, Kaizer J, Oesterle E R, Sallman A
| author name = Benney B, Kaizer J, Oesterle E, Sallman A
| author affiliation = NRC/NRR/DLP
| author affiliation = NRC/NRR/DLP
| addressee name =  
| addressee name =  
Line 9: Line 9:
| docket = PROJ0694
| docket = PROJ0694
| license number =  
| license number =  
| contact person = Benney B J
| contact person = Benney B
| package number = ML17278A096
| package number = ML17278A096
| document type = Slides and Viewgraphs
| document type = Slides and Viewgraphs
Line 16: Line 16:


=Text=
=Text=
{{#Wiki_filter:Infogram14-1 and Containment Analyses November 7, 2017 Brian Benney Ahsan Sallman Joshua KaizerEric Oesterle Objectives
{{#Wiki_filter:Infogram 14-1 and Containment Analyses November 7, 2017 Brian Benney Ahsan Sallman Joshua Kaizer Eric Oesterle
*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
Objectives
*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
* Discuss Infogram 14-1 issue
* Discuss NRC response
* Discuss Industry response
* Discuss Future Activities
* Q &A


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
Infogram 14-1
* Infograms are Westinghouse service oriented publications that discuss issues of interest to their customers
* Infogram 14-1 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


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.
NRC Response
Infogram14-1Questions?}}
* NRC learned of Infogram 14-1 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.
 
Infogram 14-1 Questions?}}

Latest revision as of 14:03, 7 January 2025

Infogram 14-1 November 7, 2017 Meeting
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

Infogram 14-1 and Containment Analyses November 7, 2017 Brian Benney Ahsan Sallman Joshua Kaizer Eric Oesterle

Objectives

  • Discuss Infogram 14-1 issue
  • Discuss NRC response
  • Discuss Industry response
  • Discuss Future Activities
  • Q &A

Infogram 14-1

  • Infograms are Westinghouse service oriented publications that discuss issues of interest to their customers
  • Infogram 14-1 identified a potential non-conservatism in containment analysis
  • Non-conservative results in post-accident containment pressures and temperatures

NRC Response

  • NRC learned of Infogram 14-1 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.

Infogram 14-1 Questions?