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| number = ML18197A411 | | number = ML18197A411 | ||
| issue date = 08/01/2018 | | issue date = 08/01/2018 | ||
| title = | | title = Supplemental Information Needed for Acceptance of Requested Licensing Action License Amendment Request to Reduce the Number of Control Element Assemblies | ||
| author name = Wentzel M | | author name = Wentzel M | ||
| author affiliation = NRC/NRR/DORL/LPLII-2 | | author affiliation = NRC/NRR/DORL/LPLII-2 | ||
| addressee name = Nazar M | | addressee name = Nazar M | ||
| Line 9: | Line 9: | ||
| docket = 05000389 | | docket = 05000389 | ||
| license number = NPF-016 | | license number = NPF-016 | ||
| contact person = Buckberg P | | contact person = Buckberg P, NRR/DORL/LPL2-2, 415-1447 | ||
| case reference number = EPID L-2018-LLA-0181 | | case reference number = EPID L-2018-LLA-0181 | ||
| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
| page count = 5 | | page count = 5 | ||
| project = EPID:L-2018-LLA-0181 | | project = EPID:L-2018-LLA-0181 | ||
| stage = | | stage = Acceptance Review | ||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 1, 2018 Mr. Mano Nazar President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd. Juno Beach, FL 33408 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 1, 2018 Mr. Mano Nazar President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd. | ||
Juno Beach, FL 33408 | |||
==SUBJECT:== | ==SUBJECT:== | ||
ST. LUCIE PLANT, UNIT NO. 2-SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REDUCE THE NUMBER OF CONTROL ELEMENT ASSEMBLIES (EPID L-2018-LLA-0181) | ST. LUCIE PLANT, UNIT NO. 2- SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REDUCE THE NUMBER OF CONTROL ELEMENT ASSEMBLIES (EPID L-2018-LLA-0181) | ||
==Dear Mr. Nazar:== | ==Dear Mr. Nazar:== | ||
By letter dated June 29, 2018 (Agencywide Documents Access and Management System Accession No. | |||
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of this license amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRG 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 10 of the Code of Federal Regulations (10 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. | By letter dated June 29, 2018 (Agencywide Documents Access and Management System Accession No. ML18180A094), Florida Power and Light Company (the licensee) submitted a license amendment request to the Technical Specifications (TSs) of Renewed Facility Operating License No. NPF-16 for St. Lucie Plant, Unit No. 2 (St. Lucie Unit 2). The proposed amendment would revise the St. Lucie Unit 2 TSs by reducing the total number of control element assemblies. | ||
Section 50.34 of 10 CFR addresses the content of technical information required. | The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of this license amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRG 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. | ||
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 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 NRG 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 proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | The NRG 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 proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | ||
In order to make the application complete, the NRG staff requests that the licensee supplement the application to address the information requested in the enclosure within 13 working days from the date of this letter (i.e., by August 20, 2018). This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not M. Nazar received by the above date, 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 application. | In order to make the application complete, the NRG staff requests that the licensee supplement the application to address the information requested in the enclosure within 13 working days from the date of this letter (i.e., by August 20, 2018). This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not | ||
If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | |||
The information requested and the associated timeframe in this letter were discussed in a conference call with Mr. Steve Catron on August 1, 2018. If you have any questions, please contact me at (301) 415-6459 or Michael.Wentzel@nrc.gov. | M. Nazar received by the above date, 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 application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | ||
Docket No. 50-389 | The information requested and the associated timeframe in this letter were discussed in a conference call with Mr. Steve Catron on August 1, 2018. | ||
If you have any questions, please contact me at (301) 415-6459 or Michael.Wentzel@nrc.gov. | |||
Sincerely, Michael J. Wentze, reject Manager Plant Licensing Br h 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389 | |||
==Enclosure:== | ==Enclosure:== | ||
Supplemental Information Needed cc: Listserv | Supplemental Information Needed cc: Listserv | ||
{TSs) of Renewed Facility Operating License No. NPF-16 for St. Lucie Plant, Unit No. 2 (St. Lucie Unit 2). The proposed amendment would revise the St. Lucie Unit 2 Technical Specifications by reducing the total number of control element assemblies. | |||
Supplemental Information Needed The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and has determined that the following additional information is necessary for the staff to make an independent assessment regarding the acceptability of the proposed amendment: | SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST TO REDUCE THE NUMBER OF CONTROL ELEMENT ASSEMBLIES FLORIDA POWER & LIGHT COMPANY, ET AL. | ||
: 1. Provide details of the St. Lucie Unit 2 specific core design and safety analysis or evaluation, including the evaluation of the Updated Final Safety Analysis (UFSAR) Chapter 15 events (ADAMS Accession Nos. | ST. LUCIE PLANT, UNIT NO. 2 DOCKET NO. 50-389 | ||
The Applicable Chapter 15 events may include, but are not limited to, the following: | |||
===Background=== | |||
By letter dated June 29, 2018 (Agencywide Documents Access and Management System Accession No. ML18180A094), Florida Power and Light Company (the licensee) submitted a license amendment request to the Technical Specifications {TSs) of Renewed Facility Operating License No. NPF-16 for St. Lucie Plant, Unit No. 2 (St. Lucie Unit 2). The proposed amendment would revise the St. Lucie Unit 2 Technical Specifications by reducing the total number of control element assemblies. | |||
Supplemental Information Needed The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and has determined that the following additional information is necessary for the staff to make an independent assessment regarding the acceptability of the proposed amendment: | |||
: 1. Provide details of the St. Lucie Unit 2 specific core design and safety analysis or evaluation, including the evaluation of the Updated Final Safety Analysis (UFSAR) | |||
Chapter 15 events (ADAMS Accession Nos. ML16194A073 and ML16194A112). The Applicable Chapter 15 events may include, but are not limited to, the following: | |||
* Section 15.1.5, "Pre-Trip Steam System Piping Failure" | * Section 15.1.5, "Pre-Trip Steam System Piping Failure" | ||
* Section 15.1.6, "Post-Trip Steam System Piping Failures" | * Section 15.1.6, "Post-Trip Steam System Piping Failures" | ||
| Line 46: | Line 54: | ||
* Section 15.4.2, "Uncontrolled Control Element Assembly Bank Withdrawal At Power" | * Section 15.4.2, "Uncontrolled Control Element Assembly Bank Withdrawal At Power" | ||
* Section 15.4.3, "Control Element Assembly (CEA) Misoperation" | * Section 15.4.3, "Control Element Assembly (CEA) Misoperation" | ||
* Section 15.4.8, "Spectrum of Control Element Assembly Ejection Accidents" The licensee's amendment request briefly describes an evaluation against the UFSAR; however, it lacks details about which of and how the Chapter 15 events have been evaluated for the reduction in the number of CEAs. The licensee's request provides no detailed information for the NRC staff to determine if the evaluation is complete and the method, as applied, is approved. | * Section 15.4.8, "Spectrum of Control Element Assembly Ejection Accidents" The licensee's amendment request briefly describes an evaluation against the UFSAR; however, it lacks details about which of and how the Chapter 15 events have been evaluated for the reduction in the number of CEAs. The licensee's request provides no detailed information for the NRC staff to determine if the evaluation is complete and the method, as applied, is approved. The regulatory basis for the information includes Appendix A to Title 1O of the Code of Federal Regulations Part 50 "General Design Criteria for Nuclear Power Plants," General Design Criteria (GDC) 10, "Reactor design," | ||
The regulatory basis for the information includes Appendix A to Title | Enclosure | ||
GDC-25 "Protection system requirements for reactivity control malfunctions," and GDC-28, "Reactivity limits." | |||
: 2. Provide details of the St. Lucie Unit 2-specific evaluation of reactor protection, control, and monitoring. The licensee's request provides no information for the NRC staff to evaluate. The regulatory basis for the information includes GDC-10, GDC-13, "Instrumentation and control," GDC-25, and GDC-28. | |||
ML18197A411 OFFICE NRR/D0RL/LPL2-2/PM NRR/D0RL/LPL2-2/LA NRR/DSS/SRXB/BC(A) | |||
NRR/D0RL/LPL2-2/PM NAME BVenkataraman MWentzel DATE 08/01/18 | NAME MWentzel BClayton (PBlechman for) JWhitman DATE 07/31/18 07/23/18 08/01/18 OFFICE NRR/D0RL/LPL2-2/BC(A) NRR/D0RL/LPL2-2/PM NAME BVenkataraman MWentzel DATE 08/01/18 08/01/18}} | ||
Latest revision as of 20:09, 20 October 2019
| ML18197A411 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/01/2018 |
| From: | Michael Wentzel Plant Licensing Branch II |
| To: | Nazar M NextEra Energy |
| Buckberg P, NRR/DORL/LPL2-2, 415-1447 | |
| References | |
| EPID L-2018-LLA-0181 | |
| Download: ML18197A411 (5) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 1, 2018 Mr. Mano Nazar President, Nuclear Division and Chief Nuclear Officer Florida Power & Light Company Mail Stop EX/JB 700 Universe Blvd.
Juno Beach, FL 33408
SUBJECT:
ST. LUCIE PLANT, UNIT NO. 2- SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REDUCE THE NUMBER OF CONTROL ELEMENT ASSEMBLIES (EPID L-2018-LLA-0181)
Dear Mr. Nazar:
By letter dated June 29, 2018 (Agencywide Documents Access and Management System Accession No. ML18180A094), Florida Power and Light Company (the licensee) submitted a license amendment request to the Technical Specifications (TSs) of Renewed Facility Operating License No. NPF-16 for St. Lucie Plant, Unit No. 2 (St. Lucie Unit 2). The proposed amendment would revise the St. Lucie Unit 2 TSs by reducing the total number of control element assemblies.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of this license amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRG 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 10 of the Code of Federal Regulations (10 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 NRG 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 proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRG staff requests that the licensee supplement the application to address the information requested in the enclosure within 13 working days from the date of this letter (i.e., by August 20, 2018). This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not
M. Nazar received by the above date, 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 application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
The information requested and the associated timeframe in this letter were discussed in a conference call with Mr. Steve Catron on August 1, 2018.
If you have any questions, please contact me at (301) 415-6459 or Michael.Wentzel@nrc.gov.
Sincerely, Michael J. Wentze, reject Manager Plant Licensing Br h 11-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-389
Enclosure:
Supplemental Information Needed cc: Listserv
SUPPLEMENTAL INFORMATION NEEDED LICENSE AMENDMENT REQUEST TO REDUCE THE NUMBER OF CONTROL ELEMENT ASSEMBLIES FLORIDA POWER & LIGHT COMPANY, ET AL.
ST. LUCIE PLANT, UNIT NO. 2 DOCKET NO. 50-389
Background
By letter dated June 29, 2018 (Agencywide Documents Access and Management System Accession No. ML18180A094), Florida Power and Light Company (the licensee) submitted a license amendment request to the Technical Specifications {TSs) of Renewed Facility Operating License No. NPF-16 for St. Lucie Plant, Unit No. 2 (St. Lucie Unit 2). The proposed amendment would revise the St. Lucie Unit 2 Technical Specifications by reducing the total number of control element assemblies.
Supplemental Information Needed The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the application and has determined that the following additional information is necessary for the staff to make an independent assessment regarding the acceptability of the proposed amendment:
- 1. Provide details of the St. Lucie Unit 2 specific core design and safety analysis or evaluation, including the evaluation of the Updated Final Safety Analysis (UFSAR)
Chapter 15 events (ADAMS Accession Nos. ML16194A073 and ML16194A112). The Applicable Chapter 15 events may include, but are not limited to, the following:
- Section 15.1.5, "Pre-Trip Steam System Piping Failure"
- Section 15.1.6, "Post-Trip Steam System Piping Failures"
- Section 15.4.1, "Uncontrolled Control Element Assembly Bank Withdrawal from a Subcritical or Low Power Startup Condition"
- Section 15.4.2, "Uncontrolled Control Element Assembly Bank Withdrawal At Power"
- Section 15.4.3, "Control Element Assembly (CEA) Misoperation"
- Section 15.4.8, "Spectrum of Control Element Assembly Ejection Accidents" The licensee's amendment request briefly describes an evaluation against the UFSAR; however, it lacks details about which of and how the Chapter 15 events have been evaluated for the reduction in the number of CEAs. The licensee's request provides no detailed information for the NRC staff to determine if the evaluation is complete and the method, as applied, is approved. The regulatory basis for the information includes Appendix A to Title 1O of the Code of Federal Regulations Part 50 "General Design Criteria for Nuclear Power Plants," General Design Criteria (GDC) 10, "Reactor design,"
Enclosure
GDC-25 "Protection system requirements for reactivity control malfunctions," and GDC-28, "Reactivity limits."
- 2. Provide details of the St. Lucie Unit 2-specific evaluation of reactor protection, control, and monitoring. The licensee's request provides no information for the NRC staff to evaluate. The regulatory basis for the information includes GDC-10, GDC-13, "Instrumentation and control," GDC-25, and GDC-28.
ML18197A411 OFFICE NRR/D0RL/LPL2-2/PM NRR/D0RL/LPL2-2/LA NRR/DSS/SRXB/BC(A)
NAME MWentzel BClayton (PBlechman for) JWhitman DATE 07/31/18 07/23/18 08/01/18 OFFICE NRR/D0RL/LPL2-2/BC(A) NRR/D0RL/LPL2-2/PM NAME BVenkataraman MWentzel DATE 08/01/18 08/01/18