ML110250187: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 28, 2011 LICENSEE: | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2011 LICENSEE: NextEra Energy Seabrook, LLC (NextEra) | ||
NextEra Energy Seabrook, LLC (NextEra) | FACILITY: Seabrook Station, Unit No.1 (Seabrook) | ||
FACILITY: | |||
Seabrook Station, Unit No.1 (Seabrook) | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF JANUARY 10, 2011, PUBLIC TELECONFERENCE WITH NEXTERA TO DISCUSS POTENTIAL SEABROOK LICENSE AMENDMENT REQUEST ON STEAM GENERATOR REPAIR CRITERIA (TAC NO. ME5282) On January 10, 2011, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra at the NRC Headquarters, 11555 Rockville Pike, Rockville, Maryland. | OF JANUARY 10, 2011, PUBLIC TELECONFERENCE WITH NEXTERA TO DISCUSS POTENTIAL SEABROOK LICENSE AMENDMENT REQUEST ON STEAM GENERATOR REPAIR CRITERIA (TAC NO. ME5282) | ||
The purpose of the meeting was to discuss NextEra's potential need for an amendment to the Seabrook Technical Specifications (TSs) governing steam generator (SG) inspection and repair. The information presented by NextEra was made available prior to the meeting in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML110050509. | On January 10, 2011, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra at the NRC Headquarters, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss NextEra's potential need for an amendment to the Seabrook Technical Specifications (TSs) governing steam generator (SG) inspection and repair. The information presented by NextEra was made available prior to the meeting in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML110050509. A list of attendees is included in the Enclosure. | ||
A list of attendees is included in the Enclosure. | The meeting was opened with a discussion of the current situation at Seabrook. Due to a single indication of outside diameter stress-corrosion cracking (ODSCC) being found during the inspection of the SGs at the last refueling outage (OR13), NextEra will need to inspect a portion of the SG tubes during the upcoming outage (OR14). Had there been no ODSCC detected during the OR13 inspection, the next SG inspection would not have occurred until the following refueling outage (OR 15). | ||
The meeting was opened with a discussion of the current situation at Seabrook. | NextEra discussed that, if primary water stress-corrosion cracking (PWSCC) were detected during this inspection, its SG inspection program would drive them to inspect additional areas of the SG tubes. Further, they indicated that although Seabrook license amendment No. 123 (ADAMS Accession No. ML092460184) modified the plugging criteria for SG inspections, it was only applicable until the next inspection of the SGs. As mentioned previously, the detection of ODSCC during the OR13 SG inspections drove the next inspection from OR15 to OR14. As a result NextEra is planning on submitting a LAR requesting approval of the alternate plugging criteria for another cycle of SG inspections. | ||
Due to a single indication of outside diameter stress-corrosion cracking (ODSCC) being found during the inspection of the SGs at the last refueling outage (OR13), NextEra will need to inspect a portion of the SG tubes during the upcoming outage (OR14). Had there been no ODSCC detected during the OR13 inspection, the next SG inspection would not have occurred until the following refueling outage (OR 15). NextEra discussed that, if primary water stress-corrosion cracking (PWSCC) were detected during this inspection, its SG inspection program would drive them to inspect additional areas of the SG tubes. Further, they indicated that although Seabrook license amendment No. 123 (ADAMS Accession No. ML092460184) modified the plugging criteria for SG inspections, it was only applicable until the next inspection of the SGs. As mentioned previously, the detection of ODSCC during the OR13 SG inspections drove the next inspection from OR15 to OR14. As a result NextEra is planning on submitting a LAR requesting approval of the alternate plugging criteria for another cycle of SG inspections. | |||
The remainder of the meeting was spent discussing the additional inspections and plugging criteria to be implemented by NextEra in the event that PWSCC is found and additional inspections are needed. This discussion focused on those additional inspections needed to support NRC staff approval of an amendment to implement the alternate repair criteria. | The remainder of the meeting was spent discussing the additional inspections and plugging criteria to be implemented by NextEra in the event that PWSCC is found and additional inspections are needed. This discussion focused on those additional inspections needed to support NRC staff approval of an amendment to implement the alternate repair criteria. | ||
Following the discussion, the meeting was opened to members of the public. No questions were received. | Following the discussion, the meeting was opened to members of the public. No questions were received. | ||
-Please direct any inquiries to me at 301-415-2481, or ed.miller@nrc.gov. | |||
G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443 List of cc w/encl: Distribution via Sign In Sheet Discussion of Potential Seabrook LAR on Steam Generator Repair Criteria DATE: January 10, 2011 Name Organization Phone Number/E-mail Address (Optional) | - 2 Please direct any inquiries to me at 301-415-2481, or ed.miller@nrc.gov. | ||
Harold Chernoff NRR/DORL Emmett Murphy NRR/DCI Robert Taylor NRR/DCI Jason Dykert NRR/DCI Kenneth Karwoski NRR/DCI Ed Miller NRR/DORL Participants via telephone Mike O'Keefe Nextera Gary Kilby Nextera Russ Lieder Nextera Mike Rocheleau Nextera | G;C:~L(C,\ | ||
G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443 | |||
==Enclosure:== | |||
*via email OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC NAME GEMilier ABaxter .. w/comment | List of Attendees cc w/encl: Distribution via Listserv | ||
{w/comment} | |||
Sign In Sheet Discussion of Potential Seabrook LAR on Steam Generator Repair Criteria DATE: January 10, 2011 Name Organization Phone Number/E-mail Address (Optional) | |||
Harold Chernoff NRR/DORL Emmett Murphy NRR/DCI Robert Taylor NRR/DCI Jason Dykert NRR/DCI Kenneth Karwoski NRR/DCI Ed Miller NRR/DORL Participants via telephone Mike O'Keefe Nextera Gary Kilby Nextera Russ Lieder Nextera Mike Rocheleau Nextera | |||
Package: ML110250155 Meeting Notice: ML103620160 Meeting Summary: ML110250187 Package Containing E-mail, Kilby, to Miller, and Information Related to Seabrook's Proposed H License Amendment Request: ML110050509 | |||
*via email OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC NAME GEMilier ABaxter .. HChernoff w/comment {w/comment} | |||
01/28/11 ! 01/28/11 01/28/11 DATE}} | |||
Revision as of 05:16, 13 November 2019
| ML110250187 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 01/28/2011 |
| From: | Geoffrey Miller Plant Licensing Branch 1 |
| To: | Office of Nuclear Reactor Regulation |
| Miller G, NRR/DORL/LPL1-2, 415-2481 | |
| Shared Package | |
| ml110250155 | List: |
| References | |
| TAC ME5282 | |
| Download: ML110250187 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 28, 2011 LICENSEE: NextEra Energy Seabrook, LLC (NextEra)
FACILITY: Seabrook Station, Unit No.1 (Seabrook)
SUBJECT:
SUMMARY
OF JANUARY 10, 2011, PUBLIC TELECONFERENCE WITH NEXTERA TO DISCUSS POTENTIAL SEABROOK LICENSE AMENDMENT REQUEST ON STEAM GENERATOR REPAIR CRITERIA (TAC NO. ME5282)
On January 10, 2011, a Category 1 public teleconference was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra at the NRC Headquarters, 11555 Rockville Pike, Rockville, Maryland. The purpose of the meeting was to discuss NextEra's potential need for an amendment to the Seabrook Technical Specifications (TSs) governing steam generator (SG) inspection and repair. The information presented by NextEra was made available prior to the meeting in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML110050509. A list of attendees is included in the Enclosure.
The meeting was opened with a discussion of the current situation at Seabrook. Due to a single indication of outside diameter stress-corrosion cracking (ODSCC) being found during the inspection of the SGs at the last refueling outage (OR13), NextEra will need to inspect a portion of the SG tubes during the upcoming outage (OR14). Had there been no ODSCC detected during the OR13 inspection, the next SG inspection would not have occurred until the following refueling outage (OR 15).
NextEra discussed that, if primary water stress-corrosion cracking (PWSCC) were detected during this inspection, its SG inspection program would drive them to inspect additional areas of the SG tubes. Further, they indicated that although Seabrook license amendment No. 123 (ADAMS Accession No. ML092460184) modified the plugging criteria for SG inspections, it was only applicable until the next inspection of the SGs. As mentioned previously, the detection of ODSCC during the OR13 SG inspections drove the next inspection from OR15 to OR14. As a result NextEra is planning on submitting a LAR requesting approval of the alternate plugging criteria for another cycle of SG inspections.
The remainder of the meeting was spent discussing the additional inspections and plugging criteria to be implemented by NextEra in the event that PWSCC is found and additional inspections are needed. This discussion focused on those additional inspections needed to support NRC staff approval of an amendment to implement the alternate repair criteria.
Following the discussion, the meeting was opened to members of the public. No questions were received.
- 2 Please direct any inquiries to me at 301-415-2481, or ed.miller@nrc.gov.
G;C:~L(C,\
G. Edward Miller, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
List of Attendees cc w/encl: Distribution via Listserv
Sign In Sheet Discussion of Potential Seabrook LAR on Steam Generator Repair Criteria DATE: January 10, 2011 Name Organization Phone Number/E-mail Address (Optional)
Harold Chernoff NRR/DORL Emmett Murphy NRR/DCI Robert Taylor NRR/DCI Jason Dykert NRR/DCI Kenneth Karwoski NRR/DCI Ed Miller NRR/DORL Participants via telephone Mike O'Keefe Nextera Gary Kilby Nextera Russ Lieder Nextera Mike Rocheleau Nextera
Package: ML110250155 Meeting Notice: ML103620160 Meeting Summary: ML110250187 Package Containing E-mail, Kilby, to Miller, and Information Related to Seabrook's Proposed H License Amendment Request: ML110050509
- via email OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC NAME GEMilier ABaxter .. HChernoff w/comment {w/comment}
01/28/11 ! 01/28/11 01/28/11 DATE