ML19247C054
| ML19247C054 | |
| Person / Time | |
|---|---|
| Site: | 99902016 |
| Issue date: | 10/09/2019 |
| From: | Joseph Holonich NRC/NRR/DLP/PLPB |
| To: | Dennis Morey NRC/NRR/DLP/PLPB |
| Holonich J, NRR/DLP/PLPB. 415-7297 | |
| References | |
| Download: ML19247C054 (2) | |
Text
October 9, 2019 MEMORANDUM TO: Dennis C. Morey, Chief Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation FROM: Joseph J. Holonich, Senior Project Manager /RA/
Licensing Processes Branch Division of Licensing Projects Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF THE SEPTEMBER 18, 2019, MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION STAFF AND WESTINGHOUSE ELECTRIC COMPANY On September 18, 2019, the U.S. Nuclear Regulatory Commission (NRC) staff met with representatives from the Westinghouse Electric Company (Westinghouse). The purpose of the meeting was to discuss the irradiated assisted stress corrosion cracking baffle bolt model.
Information related to the meeting including presentations and the attendees list can be found in the Agencywide Document Access and Management System (ADAMS) package ML19219A016.
In the opening remarks, the NRC staff stated that it was interested in understanding the Westinghouse baffle former bolt degradation model as well as any generic implications of recent baffle former bolt operating experience to the model. Westinghouse opened by stating in the meeting its objective was to show what it had done with predictive models.
During the meeting, the NRC staff and Westinghouse representatives engaged in numerous clarification discussions and questions and answers. The information discussed was proprietary, so no details of the discussions are provided.
An action identified in the meeting was from a staff question. The staff asked if Westinghouse had considered any of the Electrical Power Research Institute Materials Reliability Program topical reports when assessing stress relaxation. Westinghouse responded that it had not but committed to do so.
In closing Westinghouse informed the NRC staff that it was planning to issue a technical bulletin to plants with thermal shields and that the bulletin would recommend inspections.
Westinghouse said it would provide a copy of the bulletin to NRC staff. This is the second action from the meeting.
CONTACT: Joseph J. Holonich, NRR/DLP/PLPB 301-415-7297 Docket No. 99902016
ML19219A016 (Package);
ML19247C054 (Summary) *concurrence via e-mail NRC-001 OFFICE NRR/DLP/PLPB/PM* NRR/DMLR/MVIB/BC* NRR/DLP/PLPB/BC NRR/DLP/PLPB/PM NAME JHolonich DAlley DMorey JHolonich DATE 10/012019 10/01/2019 10/8/2019 10/9/2019