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By letter dated August 24, 2017, DTE Electric Company (DTE) submitted a license amendment request for Fermi 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17237A176). The proposed amendment would eliminate the main steam line radiation monitor (MSLRM) functions for initiating: (1) a reactor protection system automatic reactor trip and 2) the associated (Group 1) primary containment isolation system (PCIS) automatic closure of the main steam isolation valves and main steam line drain valves. Specifically, the proposed technical specification (TS) changes remove requirements for the MSLRM trip function from TS Table 3.3.1.1-1, "Reactor Protection System Instrumentation." The proposed changes also remove requirements for PCIS Group 1 isolation from TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." By letter dated October 10, 2017 (ADAMS Accession No. ML 17271A220), the U.S. Nuclear Regulatory Commission (NRG) staff notified you that we would not be able to begin our detailed review until additional information requested in the enclosure to the letter was provided. You responded to the NRC staff's request by letter dated October 18, 2017 (ML 17298A 185). The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request following your submittal of additional information. 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 NRG 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 K. Polson 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. Based on the information provided in your submittal the NRC staff has estimated that this licensing request will take approximately 1, 100 hours to complete. The NRC staff expects to complete this review in approximately 12 months, which is August 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 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 the David J. Wrona, at (301) 415-2292. Sincere! Project nager g Branch Ill Division of erating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341 cc: Distribution via Listserv | By letter dated August 24, 2017, DTE Electric Company (DTE) submitted a license amendment request for Fermi 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17237A176). The proposed amendment would eliminate the main steam line radiation monitor (MSLRM) functions for initiating: (1) a reactor protection system automatic reactor trip and 2) the associated (Group 1) primary containment isolation system (PCIS) automatic closure of the main steam isolation valves and main steam line drain valves. Specifically, the proposed technical specification (TS) changes remove requirements for the MSLRM trip function from TS Table 3.3.1.1-1, "Reactor Protection System Instrumentation." The proposed changes also remove requirements for PCIS Group 1 isolation from TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." By letter dated October 10, 2017 (ADAMS Accession No. ML 17271A220), the U.S. Nuclear Regulatory Commission (NRG) staff notified you that we would not be able to begin our detailed review until additional information requested in the enclosure to the letter was provided. You responded to the NRC staff's request by letter dated October 18, 2017 (ML 17298A 185). The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request following your submittal of additional information. 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 NRG 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 K. Polson 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. Based on the information provided in your submittal the NRC staff has estimated that this licensing request will take approximately 1, 100 hours to complete. The NRC staff expects to complete this review in approximately 12 months, which is August 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 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 the David J. Wrona, at (301) 415-2292. Sincere! Project nager g Branch Ill Division of erating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341 cc: Distribution via Listserv | ||
, ML 17297A713 OFFICE NRR/DORL/LP3/PM NRR/DORULPL3/LA NRR/DORL/LPL3/BC NAME SGoetz SRohrer DWrona DATE 10/24/2017 10/24/2017 10/24/2017 | , ML 17297A713 OFFICE NRR/DORL/LP3/PM NRR/DORULPL3/LA NRR/DORL/LPL3/BC NAME SGoetz SRohrer DWrona DATE 10/24/2017 10/24/2017 10/24/2017}} | ||
}} | |||
Revision as of 11:14, 18 May 2018
| ML17297A713 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/25/2017 |
| From: | Sujata Goetz Plant Licensing Branch III |
| To: | Polson K J DTE Electric Company |
| Goetz S | |
| References | |
| CAC MG0228, EPID L-2017-LLA-0274 | |
| Download: ML17297A713 (3) | |
Text
Mr. Keith J. Polson Senior Vice President and Chief Nuclear Officer DTE Electric Company Fermi 2 -260 TAC 6400 North Dixie Highway Newport, Ml 48166 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 25, 2017 SUBJECT FERMI 2 -ACCEPTANCE OF REQUESTED LICENSING ACTION RE: LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ELIMINATE MAIN STEAM LINE RADIATION MONITOR REACTOR TRIP AND PRIMARY CONTAINMENT ISOLATION SYSTEM GROUP 1 ISOLATION FUNCTIONS (CAC NO. MG0228, EPID L-2017-LLA-0274)
Dear Mr. Polson:
By letter dated August 24, 2017, DTE Electric Company (DTE) submitted a license amendment request for Fermi 2 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 17237A176). The proposed amendment would eliminate the main steam line radiation monitor (MSLRM) functions for initiating: (1) a reactor protection system automatic reactor trip and 2) the associated (Group 1) primary containment isolation system (PCIS) automatic closure of the main steam isolation valves and main steam line drain valves. Specifically, the proposed technical specification (TS) changes remove requirements for the MSLRM trip function from TS Table 3.3.1.1-1, "Reactor Protection System Instrumentation." The proposed changes also remove requirements for PCIS Group 1 isolation from TS Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation." By letter dated October 10, 2017 (ADAMS Accession No. ML 17271A220), the U.S. Nuclear Regulatory Commission (NRG) staff notified you that we would not be able to begin our detailed review until additional information requested in the enclosure to the letter was provided. You responded to the NRC staff's request by letter dated October 18, 2017 (ML 17298A 185). The purpose of this letter is to provide the results of the NRC staff's acceptance review of this amendment request following your submittal of additional information. 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 NRG 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 K. Polson 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. Based on the information provided in your submittal the NRC staff has estimated that this licensing request will take approximately 1, 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> to complete. The NRC staff expects to complete this review in approximately 12 months, which is August 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 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 the David J. Wrona, at (301) 415-2292. Sincere! Project nager g Branch Ill Division of erating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341 cc: Distribution via Listserv
, ML 17297A713 OFFICE NRR/DORL/LP3/PM NRR/DORULPL3/LA NRR/DORL/LPL3/BC NAME SGoetz SRohrer DWrona DATE 10/24/2017 10/24/2017 10/24/2017