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{{#Wiki_filter:}} | {{#Wiki_filter:From: Jordan, Natreon To: rdwells0@tva.gov Cc: Green, Kimberly | ||
==Subject:== | |||
Acceptance Correspondence for Application to Modify TS for Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (L-2021-LLA-0043) | |||
Date: Thursday, April 01, 2021 12:40:00 AM Mr. Wells, By {{letter dated|date=March 11, 2021|text=letter dated March 11, 2021}} (Agencywide Documents Access and Management System Accession No. ML21070A432), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) to Facility Operating License (FOL) No. NPF-96 for the Watts Bar Nuclear Plant (WBN) Unit 2 facility. The proposed amendment would delete certain WBN Unit 2 Technical Specifications (TS) for steam generator inspection and repair associated with the replacement of the WBN Unit 2 Westinghouse Model D3 (Alloy 600) original steam generators with Westinghouse Model 68AXP (Alloy 690) replacement steam generators (RSGs). This LAR also proposes to 1) revise WBN Unit 2 TS 5.7.2.12.d.2, Steam Generator (SG) Program, to reflect the TS changes in U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection," for Alloy 690 thermally treated tubing; and 2) revise WBN Unit 2 FOL Condition 2.C.(4) to delete the reference to PAD4TCD. The purpose of this correspondence is to provide the results of the NRC staffs 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 TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original application. 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 submittal and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the amendment request 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 staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence. | |||
Based on the information provided in your submittal, the NRC staff has estimated that the LAR will take approximately 230 hours to complete. The NRC staff expects to complete the review of the licensing action by March 11, 2022. 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 staffs 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 delays may occur if the submittal is provided to the NRC in advance of or in parallel with industry program initiatives or pilot applications. If you have any questions, please contact me at (301) 415-7410 or Kimberly Green at (301) 415-1627. | |||
: Thanks, | |||
-Nate Natreon (Nate) Jordan Nuclear Engineer (Project Manager) | |||
Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8B1A Washington, DC 20555 301-415-7410 natreon.jordan@nrc.gov}} |
Latest revision as of 17:06, 19 January 2022
ML21095A248 | |
Person / Time | |
---|---|
Site: | Watts Bar |
Issue date: | 04/01/2021 |
From: | Natreon Jordan Plant Licensing Branch II |
To: | Wells R Tennessee Valley Authority |
Jordan, N. | |
References | |
EPID L-2021-LLA-0043 | |
Download: ML21095A248 (2) | |
Text
From: Jordan, Natreon To: rdwells0@tva.gov Cc: Green, Kimberly
Subject:
Acceptance Correspondence for Application to Modify TS for Steam Generator Inspection/Repair Program Provisions and Unit 2 Facility Operating License Condition 2.C.(4) (L-2021-LLA-0043)
Date: Thursday, April 01, 2021 12:40:00 AM Mr. Wells, By letter dated March 11, 2021 (Agencywide Documents Access and Management System Accession No. ML21070A432), Tennessee Valley Authority (TVA, the licensee) submitted a license amendment request (LAR) to Facility Operating License (FOL) No. NPF-96 for the Watts Bar Nuclear Plant (WBN) Unit 2 facility. The proposed amendment would delete certain WBN Unit 2 Technical Specifications (TS) for steam generator inspection and repair associated with the replacement of the WBN Unit 2 Westinghouse Model D3 (Alloy 600) original steam generators with Westinghouse Model 68AXP (Alloy 690) replacement steam generators (RSGs). This LAR also proposes to 1) revise WBN Unit 2 TS 5.7.2.12.d.2, Steam Generator (SG) Program, to reflect the TS changes in U.S. Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection," for Alloy 690 thermally treated tubing; and 2) revise WBN Unit 2 FOL Condition 2.C.(4) to delete the reference to PAD4TCD. The purpose of this correspondence is to provide the results of the NRC staffs 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 TSs) must fully describe the changes requested, and following as far as applicable, the form prescribed for original application. 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 submittal and concluded that it does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the amendment request 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 staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRC staff has estimated that the LAR will take approximately 230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> to complete. The NRC staff expects to complete the review of the licensing action by March 11, 2022. 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 staffs 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 delays may occur if the submittal is provided to the NRC in advance of or in parallel with industry program initiatives or pilot applications. If you have any questions, please contact me at (301) 415-7410 or Kimberly Green at (301) 415-1627.
- Thanks,
-Nate Natreon (Nate) Jordan Nuclear Engineer (Project Manager)
Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8B1A Washington, DC 20555 301-415-7410 natreon.jordan@nrc.gov