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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 17, 2013 LICENSEE: Carolina Power & Light Company FACILITY: Brunswick Steam Electric Plant, Units 1 and 2 SUB..IECT: SUMMARY OF JANUARY 8,2013, MEETING WITH DUKE ENERGY CAROLINAS TO DISCUSS PLANNED AMENDMENT REQUESTS AT BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. MF0359 AND MF0360) On January 8, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 public meeting with Duke Energy Carolinas, LLC, representing Carolina Power & Light Company (the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland (see notice at Agencywide Documents Access and Management System (ADAMS) Accession No. ML 12346A284). The purpose of the meeting was to discuss the licensee's plans to implement amendment for the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) at Brunswick Steam Electric Plant, Units 1 and 2. The meeting provided the NRC staff an opportunity to hear the licensee's discussion of the pending changes and to ask questions about its approach. The licensee's presentation material may be accessed from the NRCs ADAMS Accession No. ML 13007 A373. The licensee's presentation generally discussed the benefits of transitioning to MELLLA+, and the approach to fuel and licensing analysis strategies, thermal hydraulic stability solution, and anticipated transient without SCRAM analysis, as well as other MELLLA+ impacts. The NRC staff asked clarifying questions throughout the presentation. The NRC staff and licensee representatives discussed the following issues, and are considering holding additional pre-application meetings to discuss the topics in more detail: The NRC staffs position that if a licensee submits a voluntary license amendment that results in a review of the containment analyses, the Emergency Core Cooling System and containment heat removal pumps' net positive shutoff head (NPSH) analyses should use the new uncertainty methods developed at NRC direction. The NRC staff, in consultation with a pump expert, determined that a 21 percent margin on the required NPSH would envelope the uncertainties. Licensees may use a lower uncertainty value, if supported by a justification that is acceptable to the NRC staff. Based on discussions during the January 8, 2013, presentation, the proposed Brunswick MELLLA+ amendment should address the new uncertainty methods. The licensee stated that the MELLLA+ application will follow approved General Electric Hitachi Nuclear Energy (GEH) generic MELLLA+ Licensing Topical Report (L TR) process (NEDC-33006P-A, "General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus). This involves GE methods and applies to GE fuel assemblies (GE-14 or Global Nuclear Fuels 2). The licensee should justify the use and applicability of the GEH generic MELLLA+
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 17, 2013 LICENSEE:       Carolina Power & Light Company FACILITY:       Brunswick Steam Electric Plant, Units 1 and 2 SUB..IECT:    
-2 LTR to the AREVA approaches and the use of AREVA fuel assemblies. The 24 imitations and conditions listed in the GEH generic MELLLA+ L TR should be addressed in the license amendment request. More detailed discussions regarding Enhanced Option III armed region and setpoint analysis with respect to its corresponding Oscillation Power Range Monitor system response (Le., is there any available Technical Specification for this application?) should be held between the NRC staff and the licensee prior to submitting the MELLLA+ application. Members of the public participated via teleconference. No Public Meeting Feedback forms were received. Please direct any inquiries to me at 301-415-1055, or Christopher.Gratton@nrc.gov. __Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-325 and List of cc w/encl: Distribution via PUBLIC MEETING WITH DUKE ENERGY BRUNSWICK UNITS 1 AND PRE-APPLICATION MEETING MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PROPOSED LICENSE JANUARY 8, LIST OF U.S. Nuclear Regulatory Commission C. Gratton K. Heller T. Huang C. Jackson A. Proffitt N. Karipineni B. Titus A. Guzzetta Progress Energy (Duke Energy Carolinas) B. Murray J. Siphers R. Thomas C. Stroupe J. Boaz J. Gee* GE Hitachi Nuclear Energy B. Berg G. Carlisle* AREVA R. DeSteese* D. Carr* D. Goodney, Constellation Energy Nuclear Group (CENG) Nine Mile Point* K. Kristensen, CENG Nine Mile Point* M. Clark, CENG Nine Mile Point*
 
* Via telephone Enclosure
==SUMMARY==
-2 LTR to the AREVA approaches and the use of AREVA fuel assemblies. The 24 imitations and conditions listed in the GEH generic MELLLA+ L TR should be addressed in the license amendment request. More detailed discussions regarding Enhanced Option III armed region and setpoint analysis with respect to its corresponding Oscillation Power Range Monitor system response (Le., is there any available Technical Specification for this application?) should be held between the NRC staff and the licensee prior to submitting the MELLLA+ application. Members of the public participated via teleconference. No Public Meeting Feedback forms were received. Please direct any inquiries to me at 301-415-1055, or Christopher.Gratton@nrc.gov. IRA! Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-325 and 50-324 Enclosure: List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION: PUBLIC LPL2-2 RlF RidsAcrsAcnw MailCTR RidsNrrDorl RidsNrrDorlLpl2-2 RidsNrrDssScvb RidsNrrDssSnpb RidsNrrDssSrxb RidsNrrLABClayton RidsNrrPMBrunswick RidsOgcRp RidsOpaMaii RidsRgn2MailCenter FKeith, NRR AGuzzetta, NRR RHannah,RII KHeller, NRR THuang, NRR NKaripineni, NRR FKeith, NRR JLedford. RII SMiranda. NRR TNakanishi, NRO MPanicker, NRR BParks, NRR AProffitt, NRR FSaba, NRR TSantos, EDO BTitus, NRR HWalker, NRR lWertz, NRR PYarsky. RES ADAMS Accession No. Package: Ml13016A019 Meeting Notice: Ml12346A284 S!ides: Ml13007A373 Summary: Ml13016A01 4 OFFICE LPlIl*2/PM LPlIl-21LA(lT) LPlIl-2/LA lPLlI-2/BC NAME FKeith BClayton FSaba for JQ DATE I 1/17113 1/17113 1/17/13 1/17113 II II OFFICIAL RECORD COpy
OF JANUARY 8,2013, MEETING WITH DUKE ENERGY CAROLINAS TO DISCUSS PLANNED AMENDMENT REQUESTS AT BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. MF0359 AND MF0360)
}}
On January 8, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 public meeting with Duke Energy Carolinas, LLC, representing Carolina Power &
Light Company (the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland (see notice at Agencywide Documents Access and Management System (ADAMS) Accession No. ML12346A284). The purpose of the meeting was to discuss the licensee's plans to implement amendment for the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) at Brunswick Steam Electric Plant, Units 1 and 2. The meeting provided the NRC staff an opportunity to hear the licensee's discussion of the pending changes and to ask questions about its approach. The licensee's presentation material may be accessed from the NRCs ADAMS Accession No. ML13007A373.
The licensee's presentation generally discussed the benefits of transitioning to MELLLA+, and the approach to fuel and licensing analysis strategies, thermal hydraulic stability solution, and anticipated transient without SCRAM analysis, as well as other MELLLA+ impacts.
The NRC staff asked clarifying questions throughout the presentation. The NRC staff and licensee representatives discussed the following issues, and are considering holding additional pre-application meetings to discuss the topics in more detail:
* The NRC staffs position that if a licensee submits a voluntary license amendment that results in a review of the containment analyses, the Emergency Core Cooling System and containment heat removal pumps' net positive shutoff head (NPSH) analyses should use the new uncertainty methods developed at NRC direction. The NRC staff, in consultation with a pump expert, determined that a 21 percent margin on the required NPSH would envelope the uncertainties.
Licensees may use a lower uncertainty value, if supported by a justification that is acceptable to the NRC staff. Based on discussions during the January 8, 2013, presentation, the proposed Brunswick MELLLA+ amendment should address the new uncertainty methods.
* The licensee stated that the MELLLA+ application will follow approved General Electric Hitachi Nuclear Energy (GEH) generic MELLLA+ Licensing Topical Report (LTR) process (NEDC-33006P-A, "General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus). This involves GE methods and applies to GE fuel assemblies (GE-14 or Global Nuclear Fuels 2). The licensee should justify the use and applicability of the GEH generic MELLLA+
 
                                          -2 LTR to the AREVA approaches and the use of AREVA fuel assemblies. The 24 imitations and conditions listed in the GEH generic MELLLA+ LTR should be addressed in the license amendment request.
* More detailed discussions regarding Enhanced Option III armed region and setpoint analysis with respect to its corresponding Oscillation Power Range Monitor system response (Le., is there any available Technical Specification for this application?) should be held between the NRC staff and the licensee prior to submitting the MELLLA+ application.
Members of the public participated via teleconference. No Public Meeting Feedback forms were received.
Please direct any inquiries to me at 301-415-1055, or Christopher.Gratton@nrc.gov.
c~ J]:; :f:~~
Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-325 and 50-324
 
==Enclosure:==
 
List of Attendees cc w/encl: Distribution via Listserv
 
PUBLIC MEETING WITH DUKE ENERGY CAROLINAS BRUNSWICK UNITS 1 AND 2 PRE-APPLICATION MEETING ON MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS PROPOSED LICENSE AMENDMENT JANUARY 8, 2013 LIST OF ATTENDEES U.S. Nuclear Regulatory Commission C. Gratton                                 K. Heller T. Huang                                   C. Jackson A. Proffitt                                 N. Karipineni B. Titus                                   A. Guzzetta Progress Energy (Duke Energy Carolinas)
B. Murray                                   J. Siphers R. Thomas                                   C. Stroupe J. Boaz                                     J. Gee*
GE Hitachi Nuclear Energy B. Berg G. Carlisle*
AREVA R. DeSteese*
D. Carr*
D. Goodney, Constellation Energy Nuclear Group (CENG) Nine Mile Point*
K. Kristensen, CENG Nine Mile Point*
M. Clark, CENG Nine Mile Point*
* Via telephone Enclosure
 
                                                    -2 LTR to the AREVA approaches and the use of AREVA fuel assemblies. The 24 imitations and conditions listed in the GEH generic MELLLA+ LTR should be addressed in the license amendment request.
* More detailed discussions regarding Enhanced Option III armed region and setpoint analysis with respect to its corresponding Oscillation Power Range Monitor system response (Le., is there any available Technical Specification for this application?) should be held between the NRC staff and the licensee prior to submitting the MELLLA+ application.
Members of the public participated via teleconference. No Public Meeting Feedback forms were received.
Please direct any inquiries to me at 301-415-1055, or Christopher.Gratton@nrc.gov.
IRA!
Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-325 and 50-324
 
==Enclosure:==
 
List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC                                 RidsOpaMaii                              TNakanishi, NRO LPL2-2 RlF                             RidsRgn2MailCenter                        MPanicker, NRR RidsAcrsAcnw MailCTR                   FKeith, NRR                               BParks, NRR RidsNrrDorl                          AGuzzetta, NRR                           AProffitt, NRR RidsNrrDorlLpl2-2                      RHannah,RII                               FSaba, NRR RidsNrrDssScvb                        KHeller, NRR                             TSantos, EDO RidsNrrDssSnpb                        THuang, NRR                               BTitus, NRR RidsNrrDssSrxb                        NKaripineni, NRR                         HWalker, NRR RidsNrrLABClayton                      FKeith, NRR                               lWertz, NRR RidsNrrPMBrunswick                    JLedford. RII                            PYarsky. RES RidsOgcRp                              SMiranda. NRR ADAMS Accession No. Package: Ml13016A019 Meeting Notice: Ml12346A284 S!ides: Ml13007A373 Summary: Ml13016A01 4 OFFICE               LPlIl*2/PM           LPlIl-21LA(lT)         LPlIl-2/LA               lPLlI-2/BC       II NAME                                       FKeith                 BClayton                 FSaba for JQ DATE               I 1/17113             1/17113               1/17/13                   1/17113         II OFFICIAL RECORD COpy}}

Latest revision as of 09:08, 6 February 2020

1/8/2013 Summary of Meeting with Progress Energy to Discuss Planned Amendment Requests at Brunswick Steam Electric Plant, Units 1 and 2
ML13016A014
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 01/17/2013
From: Gratton C
Plant Licensing Branch II
To:
Gratton, Chris
Shared Package
ML13016A019 List:
References
TAC ME3554, TAC ME3555
Download: ML13016A014 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 17, 2013 LICENSEE: Carolina Power & Light Company FACILITY: Brunswick Steam Electric Plant, Units 1 and 2 SUB..IECT:

SUMMARY

OF JANUARY 8,2013, MEETING WITH DUKE ENERGY CAROLINAS TO DISCUSS PLANNED AMENDMENT REQUESTS AT BRUNSWICK STEAM ELECTRIC PLANT, UNITS 1 AND 2 (TAC NOS. MF0359 AND MF0360)

On January 8, 2013, the U.S. Nuclear Regulatory Commission (NRC) staff conducted a Category 1 public meeting with Duke Energy Carolinas, LLC, representing Carolina Power &

Light Company (the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland (see notice at Agencywide Documents Access and Management System (ADAMS) Accession No. ML12346A284). The purpose of the meeting was to discuss the licensee's plans to implement amendment for the Maximum Extended Load Line Limit Analysis Plus (MELLLA+) at Brunswick Steam Electric Plant, Units 1 and 2. The meeting provided the NRC staff an opportunity to hear the licensee's discussion of the pending changes and to ask questions about its approach. The licensee's presentation material may be accessed from the NRCs ADAMS Accession No. ML13007A373.

The licensee's presentation generally discussed the benefits of transitioning to MELLLA+, and the approach to fuel and licensing analysis strategies, thermal hydraulic stability solution, and anticipated transient without SCRAM analysis, as well as other MELLLA+ impacts.

The NRC staff asked clarifying questions throughout the presentation. The NRC staff and licensee representatives discussed the following issues, and are considering holding additional pre-application meetings to discuss the topics in more detail:

  • The NRC staffs position that if a licensee submits a voluntary license amendment that results in a review of the containment analyses, the Emergency Core Cooling System and containment heat removal pumps' net positive shutoff head (NPSH) analyses should use the new uncertainty methods developed at NRC direction. The NRC staff, in consultation with a pump expert, determined that a 21 percent margin on the required NPSH would envelope the uncertainties.

Licensees may use a lower uncertainty value, if supported by a justification that is acceptable to the NRC staff. Based on discussions during the January 8, 2013, presentation, the proposed Brunswick MELLLA+ amendment should address the new uncertainty methods.

  • The licensee stated that the MELLLA+ application will follow approved General Electric Hitachi Nuclear Energy (GEH) generic MELLLA+ Licensing Topical Report (LTR) process (NEDC-33006P-A, "General Electric Boiling Water Reactor Maximum Extended Load Line Limit Analysis Plus). This involves GE methods and applies to GE fuel assemblies (GE-14 or Global Nuclear Fuels 2). The licensee should justify the use and applicability of the GEH generic MELLLA+

-2 LTR to the AREVA approaches and the use of AREVA fuel assemblies. The 24 imitations and conditions listed in the GEH generic MELLLA+ LTR should be addressed in the license amendment request.

  • More detailed discussions regarding Enhanced Option III armed region and setpoint analysis with respect to its corresponding Oscillation Power Range Monitor system response (Le., is there any available Technical Specification for this application?) should be held between the NRC staff and the licensee prior to submitting the MELLLA+ application.

Members of the public participated via teleconference. No Public Meeting Feedback forms were received.

Please direct any inquiries to me at 301-415-1055, or Christopher.Gratton@nrc.gov.

c~ J]:; :f:~~

Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-325 and 50-324

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv

PUBLIC MEETING WITH DUKE ENERGY CAROLINAS BRUNSWICK UNITS 1 AND 2 PRE-APPLICATION MEETING ON MAXIMUM EXTENDED LOAD LINE LIMIT ANALYSIS PLUS PROPOSED LICENSE AMENDMENT JANUARY 8, 2013 LIST OF ATTENDEES U.S. Nuclear Regulatory Commission C. Gratton K. Heller T. Huang C. Jackson A. Proffitt N. Karipineni B. Titus A. Guzzetta Progress Energy (Duke Energy Carolinas)

B. Murray J. Siphers R. Thomas C. Stroupe J. Boaz J. Gee*

GE Hitachi Nuclear Energy B. Berg G. Carlisle*

AREVA R. DeSteese*

D. Carr*

D. Goodney, Constellation Energy Nuclear Group (CENG) Nine Mile Point*

K. Kristensen, CENG Nine Mile Point*

M. Clark, CENG Nine Mile Point*

  • Via telephone Enclosure

-2 LTR to the AREVA approaches and the use of AREVA fuel assemblies. The 24 imitations and conditions listed in the GEH generic MELLLA+ LTR should be addressed in the license amendment request.

  • More detailed discussions regarding Enhanced Option III armed region and setpoint analysis with respect to its corresponding Oscillation Power Range Monitor system response (Le., is there any available Technical Specification for this application?) should be held between the NRC staff and the licensee prior to submitting the MELLLA+ application.

Members of the public participated via teleconference. No Public Meeting Feedback forms were received.

Please direct any inquiries to me at 301-415-1055, or Christopher.Gratton@nrc.gov.

IRA!

Christopher Gratton, Senior Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-325 and 50-324

Enclosure:

List of Attendees cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsOpaMaii TNakanishi, NRO LPL2-2 RlF RidsRgn2MailCenter MPanicker, NRR RidsAcrsAcnw MailCTR FKeith, NRR BParks, NRR RidsNrrDorl AGuzzetta, NRR AProffitt, NRR RidsNrrDorlLpl2-2 RHannah,RII FSaba, NRR RidsNrrDssScvb KHeller, NRR TSantos, EDO RidsNrrDssSnpb THuang, NRR BTitus, NRR RidsNrrDssSrxb NKaripineni, NRR HWalker, NRR RidsNrrLABClayton FKeith, NRR lWertz, NRR RidsNrrPMBrunswick JLedford. RII PYarsky. RES RidsOgcRp SMiranda. NRR ADAMS Accession No. Package: Ml13016A019 Meeting Notice: Ml12346A284 S!ides: Ml13007A373 Summary: Ml13016A01 4 OFFICE LPlIl*2/PM LPlIl-21LA(lT) LPlIl-2/LA lPLlI-2/BC II NAME FKeith BClayton FSaba for JQ DATE I 1/17113 1/17113 1/17/13 1/17113 II OFFICIAL RECORD COpy

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