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Date: Tuesday, August 07, 2018 10:16:44 AM Mahvash, By letter dated July 23, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18211A299), Entergy Nuclear Operations, Inc. (the licensee)submitted relief request IP3-ISI-RR-14 for U.S. Nuclear Regulatory Commission (NRC)review and approval. The licensee proposed to use Appendix I of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-729-4"Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds, Section XI." Augmented inspection in accordance with ASME Code Case N-729-4 is mandated by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(D) with conditions, and use of Appendix I requires NRC approval according to paragraph (g)(6)(ii)(D)(2) of Section 50.55a. The purpose of this e-mail is to provide the results of the NRC staff's acceptance review of this relief 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 for this licensing action. The acceptance review is also intended to identify whether the relief request has any readily apparent information insufficiencies in the characterization of the regulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your request for relief and concluded that it provides 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 relief request in terms of protection of public health and safety and the environment. | Date: Tuesday, August 07, 2018 10:16:44 AM Mahvash, By letter dated July 23, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18211A299), Entergy Nuclear Operations, Inc. (the licensee)submitted relief request IP3-ISI-RR-14 for U.S. Nuclear Regulatory Commission (NRC)review and approval. The licensee proposed to use Appendix I of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-729-4"Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds, Section XI." Augmented inspection in accordance with ASME Code Case N-729-4 is mandated by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(D) with conditions, and use of Appendix I requires NRC approval according to paragraph (g)(6)(ii)(D)(2) of Section 50.55a. The purpose of this e-mail is to provide the results of the NRC staff's acceptance review of this relief 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 for this licensing action. The acceptance review is also intended to identify whether the relief request has any readily apparent information insufficiencies in the characterization of the regulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your request for relief and concluded that it provides 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 relief request in terms of 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. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | 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. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence. | ||
Based on the information provided in your submittal, the NRC staff has estimated that the review of this relief request will take approximately | Based on the information provided in your submittal, the NRC staff has estimated that the review of this relief request will take approximately 140 hours to complete. | ||
The NRC staff expects to complete this review by February 2019. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), 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, and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications. | The NRC staff expects to complete this review by February 2019. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), 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, and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications. | ||
Please contact me if you have any questions. | Please contact me if you have any questions. | ||
A copy of this email will be made publicly available in ADAMS. ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ | A copy of this email will be made publicly available in ADAMS. ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~ | ||
Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov}} | Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov}} | ||
Revision as of 23:13, 6 November 2018
| ML18219A921 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 08/07/2018 |
| From: | Guzman R V Plant Licensing Branch 1 |
| To: | Mirzai M Entergy Nuclear Operations |
| Guzman R V | |
| References | |
| EPID: L-2018-LLR-0102 | |
| Download: ML18219A921 (2) | |
Text
From: Guzman, Richard To: Mirzai, Mahvash Cc: RidsNRRLIC109 Resource
- Walpole, Robert W
Subject:
Acceptance Review Determination: Indian Point Unit 3 - Relief Request IP3-ISI-RR-14, Proposed Alternative to ASME Code Case N-729-4; (EPID: L-2018-LLR-0102)
Date: Tuesday, August 07, 2018 10:16:44 AM Mahvash, By letter dated July 23, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18211A299), Entergy Nuclear Operations, Inc. (the licensee)submitted relief request IP3-ISI-RR-14 for U.S. Nuclear Regulatory Commission (NRC)review and approval. The licensee proposed to use Appendix I of American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code) Case N-729-4"Alternative Examination Requirements for PWR Reactor Vessel Upper Heads With Nozzles Having Pressure-Retaining Partial-Penetration Welds,Section XI." Augmented inspection in accordance with ASME Code Case N-729-4 is mandated by Title 10 of the Code of Federal Regulations (10 CFR) 50.55a(g)(6)(ii)(D) with conditions, and use of Appendix I requires NRC approval according to paragraph (g)(6)(ii)(D)(2) of Section 50.55a. The purpose of this e-mail is to provide the results of the NRC staff's acceptance review of this relief 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 for this licensing action. The acceptance review is also intended to identify whether the relief request has any readily apparent information insufficiencies in the characterization of the regulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your request for relief and concluded that it provides 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 relief request in terms of 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. You will be advised of any further information needed to support the NRC staff's detailed technical review by separate correspondence.
Based on the information provided in your submittal, the NRC staff has estimated that the review of this relief request will take approximately 140 hours0.00162 days <br />0.0389 hours <br />2.314815e-4 weeks <br />5.327e-5 months <br /> to complete.
The NRC staff expects to complete this review by February 2019. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date (greater than a month) or significant changes in the forecasted hours (greater than 25%), 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, and unanticipated addition of scope to the review. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.
Please contact me if you have any questions.
A copy of this email will be made publicly available in ADAMS. ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O-9C7 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov