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MONTHYEARULNRC-06331, Proposed Revision of Callaways FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001)2017-04-0606 April 2017 Proposed Revision of Callaways FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001) Project stage: Request ML17304B1912017-10-31031 October 2017 NRR E-mail Capture - Requests for Additional Information Concerning Callaway License Amendment - Thermal Overload Protection Project stage: RAI ML17300A2972017-11-0101 November 2017 Non-Acceptance of Relief Request RV-2 Related to Extension of Pressure Relief Valve Testing Intervals (Cac/Epid Nos. 000976/05000454/L-2017-LLR-0091 and 000976/05000455/L-2017-LLR-0091) Project stage: Acceptance Review ML17335A0442017-12-0404 December 2017 Tvel Lead Test Assembly 3rd Closed Meeting Project stage: Meeting L-17-372, Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088)2017-12-23023 December 2017 Response to Request for Additional Information Regarding Request to Use ASME Code Case N-513-4 (EPID 000976/05000334/L-2017-LLR-0088,000976/05000346/L-2017-LLR-0088, 000976/05000412/L-2017-LLR-0088, and 000976/05000440/L-2017-LLR-0088) Project stage: Response to RAI ML18010A1742018-01-10010 January 2018 NRR E-mail Capture - Braidwood, Unit 2, Acceptance Review and Resource Estimate for Relief Request I4R-07 (Cac/Epid No. 000976/05000457/L-2017-LLR-0155) Project stage: Acceptance Review ML18018B4432018-01-25025 January 2018 Summary of December 17, 2017, Closed Meeting with Exelon Generation Company, LLC, Regarding Tvel Lead Test Assemblies to Be Placed in the Braidwood Reactor (EPID 000976/05000456/L-2017-LRM and 000976/05000457/L-2017-LRM-0047 Project stage: Meeting ML18036A6672018-02-0505 February 2018 Response to Request for Additional Information Concerning Proposed Revision of Callaway'S FSAR-Described Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection (LDCN 16-0001) Project stage: Request L-18-061, Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement2018-03-16016 March 2018 Units. 1 & 2, Davis-Besse, and Perry, Response to Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement Project stage: Response to RAI L-18-125, Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/02018-05-0202 May 2018 Response to Follow-up Request for Additional Information Regarding Exemption Request for a Physical Barrier Requirement IEPID-L-2017-l-LE-0019 (CAC Nos.000976/05000334/-L-2017-LLE-0019 MG0010, 000976/05000334/L-2017-LLE-0019 MG0011,000976/0 Project stage: Request ML18129A3312018-05-0404 May 2018 Proposed Relief Request Associated with Reactor Pressure Vessel Nozzle Repairs Project stage: Request LG-18-068, Instrumentation Nozzle N-16D As-Left J-Groove Weld Analysis, Areva Document No. 32-9281804-000 (Non-Proprietary Version)2018-05-0404 May 2018 Instrumentation Nozzle N-16D As-Left J-Groove Weld Analysis, Areva Document No. 32-9281804-000 (Non-Proprietary Version) Project stage: Request ML18124A0262018-05-30030 May 2018 Issuance of Amendment No. 218 FSAR Revision Compliance with Regulatory Guide 1.106 Regarding MOV Thermal Overload Protection Project stage: Approval ML18156A4632018-06-0404 June 2018 Acceptance Review: Relief Request No. I4R-17, Revision 1, to Request Relief an Alternative to the Requirements in the ASME Code, Section XI (CAC No. 000976; EPID No. L-2018-LLR-0071) Project stage: Acceptance Review ML18221A6322018-08-15015 August 2018 Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0 Project stage: Approval ML19009A0022019-03-0505 March 2019 Issuance of Relief Request IR4-17, Revision 1, Reactor Pressure Vessel Nozzle Repair in Lieu of Specific ASME Code Requirements Project stage: Approval ML19256D4382019-09-10010 September 2019 Task Order No. 31310019F0035 Under Interagency Agreement No. 31310019N0001 Project stage: Other CNL-20-072, Tennessee Valley Authority - Bellefonte Nuclear Plant (Bln), Units 1 and 2 - Status Update and Request for Extension of Unit 1 Construction Permit CPPR-1222020-08-28028 August 2020 Tennessee Valley Authority - Bellefonte Nuclear Plant (Bln), Units 1 and 2 - Status Update and Request for Extension of Unit 1 Construction Permit CPPR-122 Project stage: Request ML20335A3932021-01-22022 January 2021 Bellefonte Nuclear Plant, Units 1 and 2 Extension of Construction Permit Expiration Dates (Cac/Epid Nos. 000976/05000438/L-2020-LLA-0214 and 000976/05000439/L 2020 Project stage: Other ML21014A3562021-01-22022 January 2021 Order - Extension of Construction Permits for Bellefonte Nuclear Plant, Units 1 and 2 Project stage: Request ML20335A3902021-01-22022 January 2021 Federal Register Notice - Order Approving the Extension of Bellefonte Units 1 and 2 Construction Permits Project stage: Request 2018-03-16
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Text
From:
Sreenivas, V To:
Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com); Stewart, Glenn H:(GenCo-Nuc)
(Glenn.Stewart@exeloncorp.com)
Cc:
Ruffin, Steve; Render, Diane; Danna, James
Subject:
Limerick Units 1 and 2: Acceptance Review: Relief Request No. I4R-17, Revision 1, to request relief an alternative to the requirements in the ASME Code,Section XI (CAC No. 000976; EPID No. L-2018-LLR-0071)
Date:
Monday, June 04, 2018 5:00:00 PM By letter dated May 4, 2018 (ADAMS Accession No. ML18129A331), Exelon Generation Company, LLC (Exelon, the licensee) requested relief from the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, 2007 Edition with 2008 Addenda at Limerick Generating Station, Unit 2.
Pursuant to Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(z)(2), Exelon submitted Relief Request No. I4R-17, Revision 1, associated with Reactor Pressure Vessel Nozzle Repairs. This request is on the basis that compliance with the ASME Code,Section XI requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality of safety. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the 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.
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 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 staffs 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 request will take approximately 200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> to complete. The NRC staff expects to complete this review in approximately 11 months, which is April 14, 2019. 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.
If you have any questions, please contact me at (301) 415-2597.
V. Sreenivas, Ph.D., C.P.M.
Licensing Project Manager Limerick and Ginna, Plant Licensing Branch I Division of Operating Reactor Licensing
Office of Nuclear Reactor Regulation