ML16294A226: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(6 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML16294A226
| number = ML16294A226
| issue date = 10/27/2016
| issue date = 10/27/2016
| title = Brunswick Steam Electric Plant, Unit Nos. 1 and 2 - Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion (CAC Nos. MF8363 and MF8364)
| title = Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion
| author name = Hon A L
| author name = Hon A
| author affiliation = NRC/NRR/DORL/LPLII-2
| author affiliation = NRC/NRR/DORL/LPLII-2
| addressee name = Gideon W R
| addressee name = Gideon W
| addressee affiliation = Duke Energy Progress, Inc
| addressee affiliation = Duke Energy Progress, Inc
| docket = 05000324, 05000325
| docket = 05000324, 05000325
| license number = DPR-062, DPR-071
| license number = DPR-062, DPR-071
| contact person = Hon A L, NRR/DORL/LPL2-2, 415-8480
| contact person = Hon A, NRR/DORL/LPL2-2, 415-8480
| case reference number = CAC MF8363, CAC MF8364
| case reference number = CAC MF8363, CAC MF8364
| document type = Letter
| document type = Letter
| page count = 4
| page count = 4
| project = CAC:MF8363, CAC:MF8364
| project = CAC:MF8363, CAC:MF8364
| stage = Supplement
| stage = Acceptance Review
}}
}}


=Text=
=Text=
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE MIC BNP001 Southport, NC 28461 October 27, 2016
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2016 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE MIC BNP001 Southport, NC 28461


==SUBJECT:==
==SUBJECT:==
BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 -
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING CORE FLOW OPERATING RANGE EXPANSION (CAC NOS. MF8363 AND MF8364)


BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 -SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING CORE FLOW OPERATING RANGE EXPANSION (CAC NOS. MF8363 AND MF8364)
==Dear Mr. Gideon:==


==Dear Mr. Gideon:==
By letter dated September 6, 2016 (Agencywide Documents Access and Management System Accession No. ML16271A187), Duke Energy submitted a license amendment request for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The proposed amendment request would revise Technical Specifications (TSs) 3.1.7, 3.3.1.1, 3.4.1, and 5.6.5; add a new TS 5.6.7; and add a new condition to Appendix B of the Renewed Facility Operating Licenses, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.
By letter dated September 6, 2016 (Agencywide Documents Access and Management System Accession No. ML 16271A187),
The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
Duke Energy submitted a license amendment request for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The proposed amendment request would revise Technical Specifications (TSs) 3.1.7, 3.3.1.1, 3.4.1, and 5.6.5; add a new TS 5.6.7; and add a new condition to Appendix B of the Renewed Facility Operating  
Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
: Licenses, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)).
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request.
The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with Section 50.90 of Title 1 O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the license amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the license amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to complete its review, the NRC staff requests that you supplement the application to address the information requested in the enclosure by November 11, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by November 11, 2016, the application will not be accepted for review pursuant to 1 O CFR 2.101, and the NRC will cease its review activities associated with the W. Gideon application.
In order to complete its review, the NRC staff requests that you supplement the application to address the information requested in the enclosure by November 11, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by November 11, 2016, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the
If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
 
The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016. In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE).
W. Gideon                                         application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts.
The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016.
Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data. If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov.
In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE). The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts. Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data.
Docket Nos. 50-325 and 50-324  
If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov.
Sincerely, Andrew Hon, 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:==
==Enclosure:==


Supplemental Information Needed cc w/encl: Distribution via Listserv Sincerely, Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DUKE ENERGY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 In order for the U.S. Nuclear Regulatory Commission (NRC) staff to ensure that with the implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+),
Supplemental Information Needed cc w/encl: Distribution via Listserv
the operations of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, will continue to be consistent with General Design Criteria 10 and 12, the applicable acceptance criteria discussed in Chapter 15 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800),
and the anticipated transient without scram (ATWS) criteria discussed in the approved MELLLA+ Licensing Topical Report, please provide the following information:
: 1. Appropriate disposition for Limitation and Condition (L&C) 9.5 -Safety Limit Minimum Critical Power Ratio 2, Duke Energy should address experience with AREVA methods in MELLLA+ at high power to flow conditions.
: 2. Appropriate disposition for L&C 9.23 -MELLLA+ Eigenvalue Tracking.
This explanation should address how the use of AREVA methods that are not covered by the General Electric-Hitachi letter will clarify L&C 9.23. 3. Differences between Unit Nos. 1 and 2 that can affect the analysis assumptions needed to be discussed for dual-unit review and approval.
: 4. A TWS instability (A TWS-1) analysis with Unit No. 2 specific assumptions.
(Because of the significant differences in turbine bypass capacities between Unit Nos. 1 and 2 and the potential impact it can have on the competing effects that can lead to the results being more limiting at higher or lower turbine bypass capacities, the NRC staff needs the ATWS-1 analysis with Unit No. 2 specific assumptions to conduct its review.)
Enclosure W. Gideon application.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016. In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE).
The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts.
Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data. If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov.
Docket Nos. 50-325 and 50-324
 
==Enclosure:==


Supplemental Information Needed cc w/encl: Distribution via Listserv DISTRIBUTION:
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DUKE ENERGY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 In order for the U.S. Nuclear Regulatory Commission (NRC) staff to ensure that with the implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+), the operations of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, will continue to be consistent with General Design Criteria 10 and 12, the applicable acceptance criteria discussed in Chapter 15 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800), and the anticipated transient without scram (ATWS) criteria discussed in the approved MELLLA+ Licensing Topical Report, please provide the following information:
PUBLIC LPL2-2 R/F RidsACRS_MailCTR Resource RidsNrr[DssSrxb Resource RidsNrrDorl Resource RidsNrrDorllpl2-2 Resource RidsNrrPMBrunswick Resource RidsNrrLABClayton Resource RidsRgn2MailCenter Resource ADAMS Accession No
: 1.      Appropriate disposition for Limitation and Condition (L&C) 9.5 - Safety Limit Minimum Critical Power Ratio 2, Duke Energy should address experience with AREVA methods in MELLLA+ at high power to flow conditions.
* ML 16294A226
: 2.      Appropriate disposition for L&C 9.23 - MELLLA+ Eigenvalue Tracking. This explanation should address how the use of AREVA methods that are not covered by the General Electric-Hitachi letter will clarify L&C 9.23.
.. OFFICE NRR/DORL/LPL2-2/PM NAME A Hon DATE 10/27/2016 OFFICE NRR/DORL/LPL2-2/BC(A)
: 3.      Differences between Unit Nos. 1 and 2 that can affect the analysis assumptions needed to be discussed for dual-unit review and approval.
NAME JDion DATE 10/27/2016 Sincerely, IRA/ Andrew Hon, Project Manager Plant Licensing Branch 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation NRR/DORL/LPL2-2/LA N RR/DSS/SRXB/BC BClayton (LRonewicz for) EOesterle 10/27/2016 10/21/2016 NRR/DORL/LPL2-2/PM A Hon 10/27/2016 OFFICIAL RECORD COPY}}
: 4.      ATWS instability (ATWS-1) analysis with Unit No. 2 specific assumptions. (Because of the significant differences in turbine bypass capacities between Unit Nos. 1 and 2 and the potential impact it can have on the competing effects that can lead to the results being more limiting at higher or lower turbine bypass capacities, the NRC staff needs the ATWS-1 analysis with Unit No. 2 specific assumptions to conduct its review.)
Enclosure
* ML16294A226 OFFICE     NRR/DORL/LPL2-2/PM             NRR/DORL/LPL2-2/LA           N RR/DSS/SRXB/BC NAME      A Hon                          BClayton (LRonewicz for)     EOesterle DATE      10/27/2016                    10/27/2016                   10/21/2016 OFFICE      NRR/DORL/LPL2-2/BC(A)          NRR/DORL/LPL2-2/PM NAME      JDion                          A Hon DATE        10/27/2016                    10/27/2016}}

Latest revision as of 23:43, 18 March 2020

Supplemental Information Needed for Acceptance of Requested Licensing Action Request for License Amendment Regarding Core Flow Operating Range Expansion
ML16294A226
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 10/27/2016
From: Andrew Hon
Plant Licensing Branch II
To: William Gideon
Duke Energy Progress
Hon A, NRR/DORL/LPL2-2, 415-8480
References
CAC MF8363, CAC MF8364
Download: ML16294A226 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 27, 2016 Mr. William R. Gideon Site Vice President Brunswick Steam Electric Plant 8470 River Rd. SE MIC BNP001 Southport, NC 28461

SUBJECT:

BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 -

SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST REGARDING CORE FLOW OPERATING RANGE EXPANSION (CAC NOS. MF8363 AND MF8364)

Dear Mr. Gideon:

By letter dated September 6, 2016 (Agencywide Documents Access and Management System Accession No. ML16271A187), Duke Energy submitted a license amendment request for the Brunswick Steam Electric Plant, Unit Nos. 1 and 2. The proposed amendment request would revise Technical Specifications (TSs) 3.1.7, 3.3.1.1, 3.4.1, and 5.6.5; add a new TS 5.6.7; and add a new condition to Appendix B of the Renewed Facility Operating Licenses, to support an expansion of the core power-flow operating range (i.e., Maximum Extended Load Line Limit Analysis Plus (MELLLA+)). The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review.

The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Consistent with Section 50.90 of Title 1O of the Code of Federal Regulations (1 O CFR), an amendment to the license (including the TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the license amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.

In order to complete its review, the NRC staff requests that you supplement the application to address the information requested in the enclosure by November 11, 2016. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by November 11, 2016, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the

W. Gideon application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.

The information requested and associated timeframe in this letter were discussed with your staff on October 19, 2016.

In addition, as we discussed with your staff at the separate audit entrance meeting on October 19. 2016, the NRC staff anticipates the backup analysis data be available under the audit process to enable the NRC to create a plant-specific computer model (TRACE). The sensitivity analyses performed with this model will enable the NRC staff to focus our review efforts. Accordingly, our final resources and schedule estimate will be contingent upon the timely availability of the plant-specific input data.

If you have any questions, please contact me (301) 415-8480 or Andrew.Hon@nrc.gov.

Sincerely, Andrew Hon, 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:

Supplemental Information Needed cc w/encl: Distribution via Listserv

SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST DUKE ENERGY BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-325 AND 50-324 In order for the U.S. Nuclear Regulatory Commission (NRC) staff to ensure that with the implementation of Maximum Extended Load Line Limit Analysis Plus (MELLLA+), the operations of the Brunswick Steam Electric Plant, Unit Nos. 1 and 2, will continue to be consistent with General Design Criteria 10 and 12, the applicable acceptance criteria discussed in Chapter 15 of the Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants (NUREG-0800), and the anticipated transient without scram (ATWS) criteria discussed in the approved MELLLA+ Licensing Topical Report, please provide the following information:

1. Appropriate disposition for Limitation and Condition (L&C) 9.5 - Safety Limit Minimum Critical Power Ratio 2, Duke Energy should address experience with AREVA methods in MELLLA+ at high power to flow conditions.
2. Appropriate disposition for L&C 9.23 - MELLLA+ Eigenvalue Tracking. This explanation should address how the use of AREVA methods that are not covered by the General Electric-Hitachi letter will clarify L&C 9.23.
3. Differences between Unit Nos. 1 and 2 that can affect the analysis assumptions needed to be discussed for dual-unit review and approval.
4. ATWS instability (ATWS-1) analysis with Unit No. 2 specific assumptions. (Because of the significant differences in turbine bypass capacities between Unit Nos. 1 and 2 and the potential impact it can have on the competing effects that can lead to the results being more limiting at higher or lower turbine bypass capacities, the NRC staff needs the ATWS-1 analysis with Unit No. 2 specific assumptions to conduct its review.)

Enclosure

  • ML16294A226 OFFICE NRR/DORL/LPL2-2/PM NRR/DORL/LPL2-2/LA N RR/DSS/SRXB/BC NAME A Hon BClayton (LRonewicz for) EOesterle DATE 10/27/2016 10/27/2016 10/21/2016 OFFICE NRR/DORL/LPL2-2/BC(A) NRR/DORL/LPL2-2/PM NAME JDion A Hon DATE 10/27/2016 10/27/2016
Retrieved from "https://kanterella.com/w/index.php?title=ML16294A226&oldid=2626840"