ML19073A017: Difference between revisions
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{{#Wiki_filter:~p. REGt, | {{#Wiki_filter:~p. REGt,1 _ | ||
--WASHINGTON, D.C. 20555-0001 -e: ,!' "" | 0 ""'1:. | ||
NextEra Energy Seabrook, LLC FACILITY: | 0 | ||
Seabrook Station, Unit No. 1 | / ~ ~\ UNITED STATES | ||
~ ] NUCLEAR REGULATORY COMMISSION | |||
- - WASHINGTON, D.C. 20555-0001 | |||
-e: ,!' | |||
"" | |||
,, ***~* +O March 21, 2019 LICENSEE: NextEra Energy Seabrook, LLC FACILITY: Seabrook Station, Unit No. 1 | |||
==SUBJECT:== | ==SUBJECT:== | ||
==SUMMARY== | ==SUMMARY== | ||
OF MARCH 11, 2019, MEETING WITH NEXTERA ENERGY SEABROOK, LLC ON PROPOSED RELIEF REQUESTS FOR THE CONTAINMENT SPRAY SYSTEM FOR THE SEABROOK STATION, UNIT N0.1 On March 11, 2019, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra Energy Seabrook, LLC (NextEra) by teleconference. | OF MARCH 11, 2019, MEETING WITH NEXTERA ENERGY SEABROOK, LLC ON PROPOSED RELIEF REQUESTS FOR THE CONTAINMENT SPRAY SYSTEM FOR THE SEABROOK STATION, UNIT N0.1 On March 11, 2019, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra Energy Seabrook, LLC (NextEra) by teleconference. The purpose of the meeting was to discuss NextEra's plans to submit two relief requests related to the containment spray system for the Seabrook Station, Unit No. 1 (Seabrook). The meeting notice and agenda, dated February 28, 2019, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19059A388. A list of attendees is enclosed with this meeting summary. | ||
The purpose of the meeting was to discuss NextEra's plans to submit two relief requests related to the containment spray system for the Seabrook Station, Unit No. 1 (Seabrook). | The licensee described its plans to submit two relief requests related to the containment spray system to the NRC by the end of March 2019. The first request would be seeking relief from the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), Appendix V, to perform a periodic verification flow test of the containment spray system. NextEra stated that its recirculation lines do not allow for full flow testing and would require significant modification within containment to provide adequate piping pathways for the flow. NextEra said the comprehensive pump tests it currently does at 68 percent of pump design flow adequately tests the pumps. NextEra pointed out this request would be a variation to a relief request previously granted to Seabrook on June 11, 2010 (ADAMS Accession No. ML101380192), regarding full-flow testing of the containment spray system. | ||
The meeting notice and agenda, dated February 28, 2019, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19059A388. | The second request would be seeking relief from the ASME OM Code vibration requirements. | ||
A list of attendees is enclosed with this meeting summary. The licensee described its plans to submit two relief requests related to the containment spray system to the NRC by the end of March 2019. The first request would be seeking relief from the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), Appendix V, to perform a periodic verification flow test of the containment spray system. NextEra stated that its recirculation lines do not allow for full flow testing and would require significant modification within containment to provide adequate piping pathways for the flow. NextEra said the comprehensive pump tests it currently does at 68 percent of pump design flow adequately tests the pumps. NextEra pointed out this request would be a variation to a relief request previously granted to Seabrook on June 11, 2010 (ADAMS Accession No. ML101380192), regarding full-flow testing of the containment spray system. The second request would be seeking relief from the ASME OM Code vibration requirements. | On June 3, 2010 (ADAMS Accession No. ML101380166), Seabrook was approved to increase the vibration alert range absolute limit from 0.325 inches per second (ips) to 0.350 ips. NextEra said this second proposed request would request to extend the limit to 0.40 ips. NextEra claimed it has operational data to show that the pumps can operate safely up to this limit. | ||
On June 3, 2010 (ADAMS Accession No. ML101380166), Seabrook was approved to increase the vibration alert range absolute limit from 0.325 inches per second (ips) to 0.350 ips. NextEra said this second proposed request would request to extend the limit to 0.40 ips. NextEra claimed it has operational data to show that the pumps can operate safely up to this limit. NextEra also stated that the vendor did an analysis to show the pumps can operate safely up to this limit as well. During NextEra's discussion of the first request, the NRC staff commented that NextEra should review NUREG-1482, Revision 2, "Guidelines for lnservice Testing at Nuclear Power Plants: lnservice Testing of Pumps and Valves and lnservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants -Final Report (ADAMS Accession No. ML13295A020), Section 5.10, "Alternative to ASME OM Code Comprehensive Pump Testing Requirements," and recommended that Seabrook's application address the seven guidelines NUREG-1482 contains for these types of relief requests. Regarding the first request, the NRC staff asked under which provision of Title | NextEra also stated that the vendor did an analysis to show the pumps can operate safely up to this limit as well. | ||
During NextEra's discussion of the first request, the NRC staff commented that NextEra should review NUREG-1482, Revision 2, "Guidelines for lnservice Testing at Nuclear Power Plants: | |||
lnservice Testing of Pumps and Valves and lnservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants - Final Report (ADAMS Accession No. ML13295A020), Section 5.10, "Alternative to ASME OM Code Comprehensive Pump Testing Requirements," and recommended that Seabrook's application address the seven guidelines NUREG-1482 contains for these types of relief requests. | |||
Regarding the first request, the NRC staff asked under which provision of Title 1O of the Code of Federal Regulations (10 CFR) Section 50.55a "Codes and standards," NextEra would be seeking relief. NextEra stated that it was planning to submit the request under 10 CFR 50.55a(z)( 1). The NRC staff recommended that NextEra review the Office of Nuclear Reactor Regulation Office Instruction LIC-102, "Relief Request Reviews" (ADAMS Accession No. ML091380595), as to whether it might be more appropriate for the application to be submitted under another section of the 1O CFR Part 50 (i.e., 10 CFR 50.55a(f)(5)). | |||
NextEra said it would take the NRC staff's recommendations into consideration as it finalizes the submittals. | NextEra said it would take the NRC staff's recommendations into consideration as it finalizes the submittals. | ||
No members of the public were in attendance; no public meeting feedback forms were received. | No members of the public were in attendance; no public meeting feedback forms were received. | ||
Please direct any inquiries to me at 301-415-2048, or Justin.Poole@nrc.gov. | Please direct any inquiries to me at 301-415-2048, or Justin.Poole@nrc.gov. | ||
Docket No. 50-443 | /' ~,----H*-*-- | ||
7 | |||
------* | |||
Justin C. Poole, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443 | |||
==Enclosure:== | ==Enclosure:== | ||
List of Attendees cc: Listserv | List of Attendees cc: Listserv | ||
LIST OF ATTENDEES MARCH 11, 2019, MEETING WITH NEXTERA ENERGY SEABROOK, LLC PROPOSED RELIEF REQUEST ON CONTAINMENT SPRAY SYSTEM FOR THE SEABROOK STATION, UNIT NO. 1 NRC Participants | |||
* Justin Poole, Project Manager, Office of Nuclear Reactor Regulations (NRR)/Division of Operating Reactor Licensing/Plant Licensing Branch I | * Justin Poole, Project Manager, Office of Nuclear Reactor Regulations (NRR)/Division of Operating Reactor Licensing/Plant Licensing Branch I | ||
* Robert Wolfgang, Senior Mechanical Engineer, NRR/Division of Engineering (DE)/Mechanical Engineering and lnservice Testing Branch (EMIB) | * Robert Wolfgang, Senior Mechanical Engineer, NRR/Division of Engineering (DE)/Mechanical Engineering and lnservice Testing Branch (EMIB) | ||
| Line 50: | Line 63: | ||
* Christine Thomas, Seabrook Licensing | * Christine Thomas, Seabrook Licensing | ||
* Brian O'Callahan, Seabrook Engineering | * Brian O'Callahan, Seabrook Engineering | ||
* James Crowley, Seabrook Engineering Enclosure | * James Crowley, Seabrook Engineering Enclosure | ||
ML19073A017 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME JPoole LRonewicz JDanna JPoole DATE 03/19/2019 03/15/2019 03/20/2019 03/21/2019}} | |||
Revision as of 00:07, 20 October 2019
| ML19073A017 | |
| Person / Time | |
|---|---|
| Site: | Seabrook  |
| Issue date: | 03/21/2019 |
| From: | Justin Poole Plant Licensing Branch 1 |
| To: | NextEra Energy Seabrook |
| Poole J, NRR/DORL/LPLI, 415-2048 | |
| References | |
| Download: ML19073A017 (4) | |
Text
~p. REGt,1 _
0 ""'1:.
0
/ ~ ~\ UNITED STATES
~ ] NUCLEAR REGULATORY COMMISSION
- - WASHINGTON, D.C. 20555-0001
-e: ,!'
""
,, ***~* +O March 21, 2019 LICENSEE: NextEra Energy Seabrook, LLC FACILITY: Seabrook Station, Unit No. 1
SUBJECT:
SUMMARY
OF MARCH 11, 2019, MEETING WITH NEXTERA ENERGY SEABROOK, LLC ON PROPOSED RELIEF REQUESTS FOR THE CONTAINMENT SPRAY SYSTEM FOR THE SEABROOK STATION, UNIT N0.1 On March 11, 2019, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of NextEra Energy Seabrook, LLC (NextEra) by teleconference. The purpose of the meeting was to discuss NextEra's plans to submit two relief requests related to the containment spray system for the Seabrook Station, Unit No. 1 (Seabrook). The meeting notice and agenda, dated February 28, 2019, are available in the Agencywide Documents Access and Management System (ADAMS) at Accession No. ML19059A388. A list of attendees is enclosed with this meeting summary.
The licensee described its plans to submit two relief requests related to the containment spray system to the NRC by the end of March 2019. The first request would be seeking relief from the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), Appendix V, to perform a periodic verification flow test of the containment spray system. NextEra stated that its recirculation lines do not allow for full flow testing and would require significant modification within containment to provide adequate piping pathways for the flow. NextEra said the comprehensive pump tests it currently does at 68 percent of pump design flow adequately tests the pumps. NextEra pointed out this request would be a variation to a relief request previously granted to Seabrook on June 11, 2010 (ADAMS Accession No. ML101380192), regarding full-flow testing of the containment spray system.
The second request would be seeking relief from the ASME OM Code vibration requirements.
On June 3, 2010 (ADAMS Accession No. ML101380166), Seabrook was approved to increase the vibration alert range absolute limit from 0.325 inches per second (ips) to 0.350 ips. NextEra said this second proposed request would request to extend the limit to 0.40 ips. NextEra claimed it has operational data to show that the pumps can operate safely up to this limit.
NextEra also stated that the vendor did an analysis to show the pumps can operate safely up to this limit as well.
During NextEra's discussion of the first request, the NRC staff commented that NextEra should review NUREG-1482, Revision 2, "Guidelines for lnservice Testing at Nuclear Power Plants:
lnservice Testing of Pumps and Valves and lnservice Examination and Testing of Dynamic Restraints (Snubbers) at Nuclear Power Plants - Final Report (ADAMS Accession No. ML13295A020), Section 5.10, "Alternative to ASME OM Code Comprehensive Pump Testing Requirements," and recommended that Seabrook's application address the seven guidelines NUREG-1482 contains for these types of relief requests.
Regarding the first request, the NRC staff asked under which provision of Title 1O of the Code of Federal Regulations (10 CFR) Section 50.55a "Codes and standards," NextEra would be seeking relief. NextEra stated that it was planning to submit the request under 10 CFR 50.55a(z)( 1). The NRC staff recommended that NextEra review the Office of Nuclear Reactor Regulation Office Instruction LIC-102, "Relief Request Reviews" (ADAMS Accession No. ML091380595), as to whether it might be more appropriate for the application to be submitted under another section of the 1O CFR Part 50 (i.e., 10 CFR 50.55a(f)(5)).
NextEra said it would take the NRC staff's recommendations into consideration as it finalizes the submittals.
No members of the public were in attendance; no public meeting feedback forms were received.
Please direct any inquiries to me at 301-415-2048, or Justin.Poole@nrc.gov.
/' ~,----H*-*--
7
*
Justin C. Poole, Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-443
Enclosure:
List of Attendees cc: Listserv
LIST OF ATTENDEES MARCH 11, 2019, MEETING WITH NEXTERA ENERGY SEABROOK, LLC PROPOSED RELIEF REQUEST ON CONTAINMENT SPRAY SYSTEM FOR THE SEABROOK STATION, UNIT NO. 1 NRC Participants
- Justin Poole, Project Manager, Office of Nuclear Reactor Regulations (NRR)/Division of Operating Reactor Licensing/Plant Licensing Branch I
- Robert Wolfgang, Senior Mechanical Engineer, NRR/Division of Engineering (DE)/Mechanical Engineering and lnservice Testing Branch (EMIB)
- Aaron Mink, Mechanical Engineer, NRR/DE/EMIB NextEra Participants
- Steve Catron, Fleet Licensing
- Jarrett Mack, Fleet Licensing
- Gary Kilby, Fleet Licensing
- Tom Ruiz, Fleet Engineering
- Tim Couture, Fleet Engineering
- Kenneth Browne, Seabrook Licensing
- Christine Thomas, Seabrook Licensing
- Brian O'Callahan, Seabrook Engineering
- James Crowley, Seabrook Engineering Enclosure
ML19073A017 OFFICE NRR/DORL/LPL 1/PM NRR/DORL/LPL 1/LA NRR/DORL/LPL 1/BC NRR/DORL/LPL 1/PM NAME JPoole LRonewicz JDanna JPoole DATE 03/19/2019 03/15/2019 03/20/2019 03/21/2019