ML18219A921: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
 
(4 intermediate revisions by the same user not shown)
Line 2: Line 2:
| number = ML18219A921
| number = ML18219A921
| issue date = 08/07/2018
| issue date = 08/07/2018
| title = Indian Point, Unit 3 - Acceptance Review Determination: Relief Request IP3-ISI-RR-14, Proposed Alternative to ASME Code Case N-729-4 (EPID: L-2018-LLR-0102)
| title = Acceptance Review Determination: Relief Request IP3-ISI-RR-14, Proposed Alternative to ASME Code Case N-729-4
| author name = Guzman R V
| author name = Guzman R
| author affiliation = NRC/NRR/DORL/LPLI
| author affiliation = NRC/NRR/DORL/LPLI
| addressee name = Mirzai M
| addressee name = Mirzai M
Line 9: Line 9:
| docket = 05000286
| docket = 05000286
| license number = DPR-064
| license number = DPR-064
| contact person = Guzman R V
| contact person = Guzman R
| case reference number = EPID: L-2018-LLR-0102
| case reference number = EPID: L-2018-LLR-0102
| document type = Acceptance Review Letter, E-Mail
| document type = Acceptance Review Letter, E-Mail
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:From: Guzman, Richard To: Mirzai, Mahvash Cc: RidsNRRLIC109 Resource
{{#Wiki_filter:From:           Guzman, Richard To:             Mirzai, Mahvash Cc:             RidsNRRLIC109 Resource; Walpole, Robert W
; Walpole, Robert W


==Subject:==
==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)
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.
Date:           Tuesday, August 07, 2018 10:16:44 AM
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.
: 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.
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 purpose of this e-mail is to provide the results of the NRC staffs 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 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 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 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.
Please contact me if you have any questions.
Based on the information provided in your submittal, the NRC staff has estimated that the review of this relief request will take approximately [[estimated NRC review hours::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%),
A copy of this email will be made publicly available in ADAMS. ~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~
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, 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}}
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}}

Latest revision as of 09:51, 6 March 2020

Acceptance Review Determination: Relief Request IP3-ISI-RR-14, Proposed Alternative to ASME Code Case N-729-4
ML18219A921
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 08/07/2018
From: Richard Guzman
Plant Licensing Branch 1
To: Mirzai M
Entergy Nuclear Operations
Guzman R
References
EPID: L-2018-LLR-0102
Download: ML18219A921 (2)
v • d • e


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 staffs 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 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 review of this relief request will take approximately 140 hours5.833 days <br />0.833 weeks <br />0.192 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 staffs 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

Retrieved from "https://kanterella.com/w/index.php?title=ML18219A921&oldid=2527642"