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| | number = ML17017A109 | | | number = ML17017A109 |
| | issue date = 01/24/2017 | | | issue date = 01/24/2017 |
| | title = Nine Mile Point Nuclear Station, Unit 1 - Acceptance of Requested Licensing Action Partial Length Fuel Rod Burnup (CAC No. MF9046) | | | title = Acceptance of Requested Licensing Action Partial Length Fuel Rod Burnup |
| | author name = Marshall M L | | | author name = Marshall M |
| | author affiliation = NRC/NRR/DORL/LPLI | | | author affiliation = NRC/NRR/DORL/LPLI |
| | addressee name = Hanson B C | | | addressee name = Hanson B |
| | addressee affiliation = Exelon Nuclear Generation Corp | | | addressee affiliation = Exelon Nuclear Generation Corp |
| | docket = 05000220 | | | docket = 05000220 |
| | license number = DPR-063 | | | license number = DPR-063 |
| | contact person = Marshall M L, NRR-DORL-LPL1, 415-2871 | | | contact person = Marshall M, NRR-DORL-LPL1, 415-2871 |
| | case reference number = CAC MF9046 | | | case reference number = CAC MF9046 |
| | document type = Acceptance Review Letter | | | document type = Acceptance Review Letter |
| | page count = 3 | | | page count = 3 |
| | project = CAC:MF9046 | | | project = CAC:MF9046 |
| | stage = Other | | | stage = Acceptance Review |
| }} | | }} |
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| =Text= | | =Text= |
| {{#Wiki_filter:Mr. Bryan C. Hanson UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 24, 2017 President and Chief Nuclear Officer Exelon Nuclear Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 SUBJECT: NINE MILE POINT NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: PARTIAL LENGTH FUEL ROD BURNUP (CAC NO. MF9046) Dear Mr. Hanson: By letter dated January 3, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17003A065), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 1. The proposed amendment would allow the use of release fractions listed in Tables 1 and 3 of NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" (ADAMS Accession No. ML003716792), for partial length fuel rods that are operating above the peak burnup limit, through the end of Operating Cycle 22. 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 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) 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 it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and 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. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified, despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 24, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555 |
| B. Hanson -2 -Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 75 hours to complete. The NRC staff expects to complete this review by March 10, 2017 (approximately 2 months). If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager. These estimates are based on the NRC staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance, or in parallel with, industry program initiatives or pilot applications. If you have any questions, please contact me at (301) 415-2871 or Michael.Marshall@nrc.gov. Docket No. 50-220 cc: Distribution via Listserv Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation B. Hanson -2 -completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager. These estimates are based on the NRC staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance, or in parallel with, industry program initiatives or pilot applications. If you have any questions, please contact me at (301) 415-2871 or Michael.Marshall@nrc.gov. Docket No. 50-220 cc: Distribution via Listserv DISTRIBUTION: PUBLIC SKrepel, NRR LPL 1 R/F JWhitman, NRR RidsACRS_MailCTR Sincerely, /RAJ Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation JParillo, NRR RidsNrrDorl Resource RidsNrrDorlLpl1 Resource RidsNrrLALRonewicz RidsNrrPMNineMilePoint RidsRgn1 MailCenter RidsNrrDssSnpb Resource RidsNrrDssSrxb Resource RidsNrrDraArcb Resource ADAMS Accession No.: ML 17017A109 OFFICE DORL/LPL 1/PM DORL/LPL 1/PM DORL/LPL 1/LA DORL/LPL 1/BC(A) DORL/LPL 1/PM NAME MMarshall RGuzman LRonewicz SKoenick MMarshall DATE 1/19/2017 1/23/2017 1/19/2017 1/24/2017 1/24/2017 OFFICIAL RECORD COPY | | |
| }} | | ==SUBJECT:== |
| | NINE MILE POINT NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: PARTIAL LENGTH FUEL ROD BURNUP (CAC NO. MF9046) |
| | |
| | ==Dear Mr. Hanson:== |
| | |
| | By letter dated January 3, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17003A065), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 1. The proposed amendment would allow the use of release fractions listed in Tables 1 and 3 of NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" (ADAMS Accession No. ML003716792), for partial length fuel rods that are operating above the peak burnup limit, through the end of Operating Cycle 22. 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 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) 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 it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and 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. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified, despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence. |
| | |
| | B. Hanson Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately [[estimated NRC review hours::75 hours]] to complete. The NRC staff expects to complete this review by March 10, 2017 (approximately 2 months). If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager. |
| | These estimates are based on the NRC staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance, or in parallel with, industry program initiatives or pilot applications. |
| | If you have any questions, please contact me at (301) 415-2871 or Michael.Marshall@nrc.gov. |
| | Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 cc: Distribution via Listserv |
| | |
| | ML17017A109 OFFICE DORL/LPL 1/PM DORL/LPL 1/PM DORL/LPL 1/LA DORL/LPL 1/BC(A) DORL/LPL 1/PM NAME MMarshall RGuzman LRonewicz SKoenick MMarshall DATE 1/19/2017 1/23/2017 1/19/2017 1/24/2017 1/24/2017}} |
Letter Sequence Acceptance Review |
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Category:Acceptance Review Letter
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[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 24, 2017 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
NINE MILE POINT NUCLEAR STATION, UNIT 1 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: PARTIAL LENGTH FUEL ROD BURNUP (CAC NO. MF9046)
Dear Mr. Hanson:
By letter dated January 3, 2017 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML17003A065), Exelon Generation Company, LLC submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 1. The proposed amendment would allow the use of release fractions listed in Tables 1 and 3 of NRC Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors" (ADAMS Accession No. ML003716792), for partial length fuel rods that are operating above the peak burnup limit, through the end of Operating Cycle 22. 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 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) 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 it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and 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. Given the lesser scope and depth of the acceptance review, as compared to the detailed technical review, there may be instances in which issues that impact the NRC staff's ability to complete the detailed technical review are identified, despite completion of an adequate acceptance review. If additional information is needed, you will be advised by separate correspondence.
B. Hanson Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 75 hours3.125 days <br />0.446 weeks <br />0.103 months <br /> to complete. The NRC staff expects to complete this review by March 10, 2017 (approximately 2 months). If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated during the routine interactions with the assigned project manager.
These estimates are based on the NRC staff's initial review of the application and they could change due to several factors, including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance, or in parallel with, industry program initiatives or pilot applications.
If you have any questions, please contact me at (301) 415-2871 or Michael.Marshall@nrc.gov.
Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-220 cc: Distribution via Listserv
ML17017A109 OFFICE DORL/LPL 1/PM DORL/LPL 1/PM DORL/LPL 1/LA DORL/LPL 1/BC(A) DORL/LPL 1/PM NAME MMarshall RGuzman LRonewicz SKoenick MMarshall DATE 1/19/2017 1/23/2017 1/19/2017 1/24/2017 1/24/2017
