ML17271A259: Difference between revisions
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| number = ML17271A259 | | number = ML17271A259 | ||
| issue date = 10/10/2017 | | issue date = 10/10/2017 | ||
| title = | | title = Acceptance for Review of Application Concerning Revision to MCPR Safety Limits in Technical Specification 2.1.1 | ||
| author name = Vaidya B | | author name = Vaidya B | ||
| author affiliation = NRC/NRR/DORL/LPLIII | | author affiliation = NRC/NRR/DORL/LPLIII | ||
| addressee name = Hanson B | | addressee name = Hanson B | ||
| addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | | addressee affiliation = Exelon Generation Co, LLC, Exelon Nuclear | ||
| docket = 05000373, 05000374 | | docket = 05000373, 05000374 | ||
| license number = NPF-011, NPF-018 | | license number = NPF-011, NPF-018 | ||
| contact person = Vaidya B | | contact person = Vaidya B | ||
| case reference number = CAC MG0211, CAC MG0212 | | case reference number = CAC MG0211, CAC MG0212 | ||
| document type = Acceptance Review Letter | | document type = Acceptance Review Letter | ||
| page count = 3 | | page count = 3 | ||
| project = CAC:MG0211, CAC:MG0212 | | project = CAC:MG0211, CAC:MG0212 | ||
| stage = Acceptance Review | |||
}} | }} | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1 0, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO) | ||
B. Hanson | Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | ||
}} | |||
==SUBJECT:== | |||
LASALLE COUNTY STATION, UNITS 1 AND 2, ACCEPTANCE FOR REVIEW OF APPLICATION CONCERNING REVISION TO MCPR SAFETY LIMITS IN TECHNICAL SPECIFICATION 2.1.1 (CAC NOS. MG0211 AND MG0212) | |||
==Dear Mr. Hanson:== | |||
By letter dated October 27, 2016, Exelon Generation Company, LLC (EGG) submitted an amendment request for the LaSalle County Station, Units 1 and 2. The proposed amendments would revise the LaSalle County Station (LSCS) Technical Specifications (TSs) 2.1.1, "Reactor Core SLs [Safety Limits]," for LSCS, Units 1 and 2. Specifically, this change incorporates revised LSCS, Units 1 and 2, safety limit for minimum critical power ratio (SLMCPR) for two circulation loop MCPR and single circulation loop MCPR values for Unit 1 and Unit 2 based on the results of the cycle-specific analyses performed by Global Nuclear Fuel (GNF) for LSCS Unit 1, Cycle 17, and LSCS Unit 2, Cycle 17. | |||
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of the proposed 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 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. | |||
B. Hanson The NRG staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRG 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 NRG 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. | |||
Based on the information provided in your submittal, the NRG staff has estimated that this licensing request will take approximately [[estimated NRC review hours::480 hours]] to complete. The NRG staff expects to complete this review by the requested date of February 7, 2018. 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 NRG 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 NRG advisory committees or hearing-related activities. Additional delay may occur it the submittal is provided to the NRG in advance or in parallel with industry program initiatives or pilot applications. | |||
It you have any questions, please contact me at (301) 415-3308. | |||
Sincerely, | |||
~~~ | |||
~ | |||
Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-37 4 cc: Distribution via ListServ | |||
B_ Hanson | |||
==SUBJECT:== | |||
LASALLE COUNTY STATION, UNITS 1AND2, ACCEPTANCE FOR REVIEW OF APPLICATION CONCERNING REVISION TO MCPR SAFETY LIMITS IN TECHNICAL SPECIFICATION 2.1.1 (CAC NOS. MG0211 AND MG0212) | |||
DATED OCTOBER 10, 2017 DISTRIBUTION: | |||
PUBLIC RidsNrrDssSrxb Resource RidsNrrPMLaSalle Resource RidsNrrLASRohrer Resource RidsRgn3MaifCenter Resource RidsAcrs_MailCTR Resource RidsOgcRp Resource ASallman, NRR RidsNrrOorllpl3 Resource ADAMS Accession* ML17271A259 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME BVaidya SRohrer DWrona BVaidya DATE 10/02/17 10/02/17 10/10/17 10/10/17 OFFICIAL RECORD COPY}} |
Latest revision as of 11:15, 18 March 2020
ML17271A259 | |
Person / Time | |
---|---|
Site: | LaSalle |
Issue date: | 10/10/2017 |
From: | Bhalchandra Vaidya Plant Licensing Branch III |
To: | Bryan Hanson Exelon Generation Co, Exelon Nuclear |
Vaidya B | |
References | |
CAC MG0211, CAC MG0212 | |
Download: ML17271A259 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 1 0, 2017 Mr. Bryan C. Hanson Senior Vice President Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO)
Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2, ACCEPTANCE FOR REVIEW OF APPLICATION CONCERNING REVISION TO MCPR SAFETY LIMITS IN TECHNICAL SPECIFICATION 2.1.1 (CAC NOS. MG0211 AND MG0212)
Dear Mr. Hanson:
By letter dated October 27, 2016, Exelon Generation Company, LLC (EGG) submitted an amendment request for the LaSalle County Station, Units 1 and 2. The proposed amendments would revise the LaSalle County Station (LSCS) Technical Specifications (TSs) 2.1.1, "Reactor Core SLs [Safety Limits]," for LSCS, Units 1 and 2. Specifically, this change incorporates revised LSCS, Units 1 and 2, safety limit for minimum critical power ratio (SLMCPR) for two circulation loop MCPR and single circulation loop MCPR values for Unit 1 and Unit 2 based on the results of the cycle-specific analyses performed by Global Nuclear Fuel (GNF) for LSCS Unit 1, Cycle 17, and LSCS Unit 2, Cycle 17.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRG) staff's acceptance review of the proposed 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 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.
B. Hanson The NRG staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRG 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 NRG 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.
Based on the information provided in your submittal, the NRG staff has estimated that this licensing request will take approximately 480 hours20 days <br />2.857 weeks <br />0.658 months <br /> to complete. The NRG staff expects to complete this review by the requested date of February 7, 2018. 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 NRG 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 NRG advisory committees or hearing-related activities. Additional delay may occur it the submittal is provided to the NRG in advance or in parallel with industry program initiatives or pilot applications.
It you have any questions, please contact me at (301) 415-3308.
Sincerely,
~~~
~
Bhalchandra Vaidya, Project Manager Plant Licensing Branch Ill Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-373 and 50-37 4 cc: Distribution via ListServ
B_ Hanson
SUBJECT:
LASALLE COUNTY STATION, UNITS 1AND2, ACCEPTANCE FOR REVIEW OF APPLICATION CONCERNING REVISION TO MCPR SAFETY LIMITS IN TECHNICAL SPECIFICATION 2.1.1 (CAC NOS. MG0211 AND MG0212)
DATED OCTOBER 10, 2017 DISTRIBUTION:
PUBLIC RidsNrrDssSrxb Resource RidsNrrPMLaSalle Resource RidsNrrLASRohrer Resource RidsRgn3MaifCenter Resource RidsAcrs_MailCTR Resource RidsOgcRp Resource ASallman, NRR RidsNrrOorllpl3 Resource ADAMS Accession* ML17271A259 OFFICE NRR/DORL/LPL3/PM NRR/DORL/LPL3/LA NRR/DORL/LPL3/BC NRR/DORL/LPL3/PM NAME BVaidya SRohrer DWrona BVaidya DATE 10/02/17 10/02/17 10/10/17 10/10/17 OFFICIAL RECORD COPY