ML18323A188: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:From: Hall, Randy To: JAMIEMCO@SOUTHERNCO.COM Cc: Joyce, Ryan M. (RMJOYCE@southernco.com) | {{#Wiki_filter:From: Hall, Randy To: JAMIEMCO@SOUTHERNCO.COM Cc: Joyce, Ryan M. (RMJOYCE@southernco.com) | ||
==Subject:== | ==Subject:== | ||
NRC Acceptance Review for Hatch Unit 2 Relief Request HNP-ISI-RR-05-02 (EPID L-2018-LLR-0137) | NRC Acceptance Review for Hatch Unit 2 Relief Request HNP-ISI-RR-05-02 (EPID L-2018-LLR-0137) | ||
Date: Monday, November 19, 2018 10:21:00 AM November 19, 2018 Ms. Jamie Coleman Licensing Manager Southern Nuclear Operating Company | Date: Monday, November 19, 2018 10:21:00 AM November 19, 2018 Ms. Jamie Coleman Licensing Manager Southern Nuclear Operating Company | ||
==Dear Ms. Coleman,== | ==Dear Ms. Coleman,== | ||
By letter dated November 5, 2018, Southern Nuclear Operating Company, Inc. (SNC) submitted relief request HNP-ISI-RR-05-02, requesting relief from certain inservice inspection (ISI) requirements of Section XI of the 2007 Edition through the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV), for the Edwin I. Hatch Nuclear Plant (HNP), Unit No. 2. | By letter dated November 5, 2018, Southern Nuclear Operating Company, Inc. (SNC) submitted relief request HNP-ISI-RR-05-02, requesting relief from certain inservice inspection (ISI) requirements of Section XI of the 2007 Edition through the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV), for the Edwin I. Hatch Nuclear Plant (HNP), Unit No. 2. | ||
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50.55a(g)(5)(iii), the licensee requested relief from the required surface examination of ASME BPV Code IWB 3515.2(c), which specifies surface examination requirements for the reactor pressure vessel (RPV) studs. | Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50.55a(g)(5)(iii), the licensee requested relief from the required surface examination of ASME BPV Code IWB 3515.2(c), which specifies surface examination requirements for the reactor pressure vessel (RPV) studs. HNP Unit No. 2 RPV stud no. 33 could not be removed during the previous refueling outage for the required examination, and the U.S. | ||
HNP Unit No. 2 RPV stud no. 33 could not be removed during the previous refueling outage for the required examination, and the U.S. | Nuclear Regulatory Commission (NRC) staff granted the licensees previous relief request for this same issue in a letter dated August 10, 2017. The licensee plans to remove RPV stud no. 33 and conduct the required examination during the upcoming HNP Unit 2 refueling outage scheduled to begin on February 4, 2019. However, in the event that the licensee is again unable to remove RPV stud no. 33, the licensee maintains that compliance with the Code-required examination would be impractical, and the subject relief is requested as a contingency. | ||
Nuclear Regulatory Commission (NRC) staff granted the | The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this proposed 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. 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 licensee plans to remove RPV stud no. 33 and conduct the required examination during the upcoming HNP Unit 2 refueling outage scheduled to begin on February 4, 2019. | The NRC staff has reviewed the submittal 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 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. If additional information is needed, you will be advised by separate correspondence. | ||
However, in the event that the licensee is again unable to remove RPV stud no. 33, the licensee maintains that compliance with the Code-required examination would be impractical, and the subject relief is requested as a contingency. | Based on the information provided in your submittal, the NRC staff has estimated that this | ||
The purpose of this e-mail is to provide the results of the NRC | |||
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. | licensing request will take approximately 120 hours to complete. The NRC staff expects to complete this review by February 4, 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. | ||
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. | 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. | ||
The NRC staff has reviewed the submittal 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 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 | |||
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 120 hours to complete. | |||
The NRC staff expects to complete this review by February 4, 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 | |||
If you have any questions, please contact me at (301) 415-4032. | If you have any questions, please contact me at (301) 415-4032. | ||
Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov}} | Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov}} | ||
Revision as of 11:28, 20 October 2019
| ML18323A188 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 11/19/2018 |
| From: | Randy Hall Plant Licensing Branch II |
| To: | Coleman J Southern Nuclear Operating Co |
| Hall R | |
| References | |
| EPID L-2018-LLR-0137 | |
| Download: ML18323A188 (2) | |
Text
From: Hall, Randy To: JAMIEMCO@SOUTHERNCO.COM Cc: Joyce, Ryan M. (RMJOYCE@southernco.com)
Subject:
NRC Acceptance Review for Hatch Unit 2 Relief Request HNP-ISI-RR-05-02 (EPID L-2018-LLR-0137)
Date: Monday, November 19, 2018 10:21:00 AM November 19, 2018 Ms. Jamie Coleman Licensing Manager Southern Nuclear Operating Company
Dear Ms. Coleman,
By letter dated November 5, 2018, Southern Nuclear Operating Company, Inc. (SNC) submitted relief request HNP-ISI-RR-05-02, requesting relief from certain inservice inspection (ISI) requirements of Section XI of the 2007 Edition through the 2008 Addenda of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (BPV), for the Edwin I. Hatch Nuclear Plant (HNP), Unit No. 2.
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR) Part 50.55a(g)(5)(iii), the licensee requested relief from the required surface examination of ASME BPV Code IWB 3515.2(c), which specifies surface examination requirements for the reactor pressure vessel (RPV) studs. HNP Unit No. 2 RPV stud no. 33 could not be removed during the previous refueling outage for the required examination, and the U.S.
Nuclear Regulatory Commission (NRC) staff granted the licensees previous relief request for this same issue in a letter dated August 10, 2017. The licensee plans to remove RPV stud no. 33 and conduct the required examination during the upcoming HNP Unit 2 refueling outage scheduled to begin on February 4, 2019. However, in the event that the licensee is again unable to remove RPV stud no. 33, the licensee maintains that compliance with the Code-required examination would be impractical, and the subject relief is requested as a contingency.
The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of this proposed 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. 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 the submittal 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 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. 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 120 hours0.00139 days <br />0.0333 hours <br />1.984127e-4 weeks <br />4.566e-5 months <br /> to complete. The NRC staff expects to complete this review by February 4, 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, and unanticipated addition of scope to the review.
If you have any questions, please contact me at (301) 415-4032.
Sincerely, Randy Hall, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov