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| | number = ML18135A409 | | | number = ML18135A409 |
| | issue date = 05/11/2018 | | | issue date = 05/11/2018 |
| | title = Hatch Nuclear Plant Units 1 & 2 - Acceptance for Review of Request for Alternative RR-V-12 Regarding Main Steam SRV Testing (EPID No. L-2018-LLR-0054) | | | title = Acceptance for Review of Request for Alternative RR-V-12 Regarding Main Steam SRV Testing |
| | author name = Hall J R | | | author name = Hall J |
| | author affiliation = NRC/NRR/DORL/LPLIII | | | author affiliation = NRC/NRR/DORL/LPLIII |
| | addressee name = Coleman J M | | | addressee name = Coleman J |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000321, 05000366 | | | docket = 05000321, 05000366 |
| | license number = DPR-057, NPF-005 | | | license number = DPR-057, NPF-005 |
| | contact person = Hall J R | | | contact person = Hall J |
| | case reference number = EPID L-2018-LLR-0054 | | | case reference number = EPID L-2018-LLR-0054 |
| | document type = Acceptance Review Letter, E-Mail | | | document type = Acceptance Review Letter, E-Mail |
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| =Text= | | =Text= |
| {{#Wiki_filter:From:Hall, RandyTo:JAMIEMCO@SOUTHERNCO.COMCc:Ken McElroy; Joyce, Ryan M. (RMJOYCE@southernco.com) | | {{#Wiki_filter:From: Hall, Randy To: JAMIEMCO@SOUTHERNCO.COM Cc: Ken McElroy; Joyce, Ryan M. (RMJOYCE@southernco.com) |
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| ==Subject:== | | ==Subject:== |
| Hatch Nuclear Plant Units 1 & 2 - Acceptance for Review of Request for Alternative RR-V-12 regarding MainSteam SRV Testing (EPID No. L-2018-LLR-0054)Date:Friday, May 11, 2018 8:33:00 AM May 11, 2018 Ms. Jamie M. ColemanLicensing ManagerSouthern Nuclear Operating Company | | Hatch Nuclear Plant Units 1 & 2 - Acceptance for Review of Request for Alternative RR-V-12 regarding Main Steam SRV Testing (EPID No. L-2018-LLR-0054) |
| | Date: Friday, May 11, 2018 8:33:00 AM May 11, 2018 Ms. Jamie M. Coleman Licensing Manager Southern Nuclear Operating Company |
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| ==Dear Jamie,== | | ==Dear Jamie,== |
| By letter dated April 9, 2018 (Agencywide Documents Access and Management SystemAccession No. ML18099A146), the Southern Nuclear Operating Company, Inc. (SNC, thelicensee) submitted a request for alternative to the requirements of ASME OM Code, 2004Edition through the 2006 Addenda, for the Edwin I. Hatch Nuclear Plant, Units 1 and 2. The ASME OM Code requires that Class 1 pressure relief valves shall be tested at leastonce every 5 years, with a minimum of 20% of the valves from each valve group required tobe tested within any 24-month period. SNC's proposed alternative RR-V-12 would extendthe frequency for testing all main steam safety relief valves (SRV) for each unit from onceevery 5 years to once every three refueling cycles (i.e., six years), as allowed by CodeCase OM-17. Pursuant to 10 CFR 50.55a(z)(2), SNC is requesting NRC authorization ofthis alternative on the basis that compliance with the specified requirements would result ina hardship or unusual difficulty without a compensating increase in the level of quality andsafety. The purpose of this email is to provide the results of the U.S. Nuclear RegulatoryCommission (NRC) staff's acceptance review of this request for alternative to the ASMECode requirements. The acceptance review was performed to determine if there issufficient technical information in scope and depth to allow the NRC staff to complete itsdetailed technical review. The acceptance review is also intended to identify whether theapplication has any readily apparent information insufficiencies in its characterization of theregulatory requirements or the licensing basis of the plant. The NRC staff has reviewed your application and concluded that it does provide technicalinformation in sufficient detail to enable the NRC staff to complete its detailed technicalreview and make an independent assessment regarding the acceptability of the proposedalternative in terms of regulatory requirements and the protection of public health andsafety and the environment. Given the lesser scope and depth of the acceptance review ascompared to the detailed technical review, there may be instances in which issues thatimpact the NRC staff's ability to complete the detailed technical review are identifieddespite 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 thislicensing request will take approximately 100 hours to complete. The NRC staff expects tocomplete this review within 9 months, which is generally consistent with your requested approval date of January 25, 2019. If there are emergent complexities or challenges in ourreview that would cause changes to the initial forecasted completion date or significantchanges in the forecasted hours, the reasons for the changes, along with the newestimates, will be communicated during the routine interactions with the assigned projectmanager. These estimates are based on the NRC staff's initial review of the application and theycould change, due to several factors including requests for additional information,unanticipated addition of scope to the review, and review by NRC advisory committees orhearing-related activities. If you have any questions, please contact me at (301) 415-4032. Sincerely, Randy Hall, Senior Project ManagerPlant Licensing Branch II-1Division of Operating Reactor LicensingOffice of Nuclear Reactor RegulationUSNRC(301) 415-4032Randy.Hall@nrc.gov}} | | |
| | By letter dated April 9, 2018 (Agencywide Documents Access and Management System Accession No. ML18099A146), the Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a request for alternative to the requirements of ASME OM Code, 2004 Edition through the 2006 Addenda, for the Edwin I. Hatch Nuclear Plant, Units 1 and 2. |
| | The ASME OM Code requires that Class 1 pressure relief valves shall be tested at least once every 5 years, with a minimum of 20% of the valves from each valve group required to be tested within any 24-month period. SNCs proposed alternative RRV12 would extend the frequency for testing all main steam safety relief valves (SRV) for each unit from once every 5 years to once every three refueling cycles (i.e., six years), as allowed by Code Case OM-17. Pursuant to 10 CFR 50.55a(z)(2), SNC is requesting NRC authorization of this alternative on the basis that compliance with the specified requirements would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| | The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this request for alternative to the ASME Code requirements. 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 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 independent assessment regarding the acceptability of the proposed alternative 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 [[estimated NRC review hours::100 hours]] to complete. The NRC staff expects to complete this review within 9 months, which is generally consistent with your requested |
| | |
| | approval date of January 25, 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) 415-4032. |
| | 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}} |
Letter Sequence Acceptance Review |
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EPID:L-2018-LLR-0054, Proposed Alternative RR-V-12 Regarding Main Steam Safety Relief Valve Testing (Open) |
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Text
From: Hall, Randy To: JAMIEMCO@SOUTHERNCO.COM Cc: Ken McElroy; Joyce, Ryan M. (RMJOYCE@southernco.com)
Subject:
Hatch Nuclear Plant Units 1 & 2 - Acceptance for Review of Request for Alternative RR-V-12 regarding Main Steam SRV Testing (EPID No. L-2018-LLR-0054)
Date: Friday, May 11, 2018 8:33:00 AM May 11, 2018 Ms. Jamie M. Coleman Licensing Manager Southern Nuclear Operating Company
Dear Jamie,
By letter dated April 9, 2018 (Agencywide Documents Access and Management System Accession No. ML18099A146), the Southern Nuclear Operating Company, Inc. (SNC, the licensee) submitted a request for alternative to the requirements of ASME OM Code, 2004 Edition through the 2006 Addenda, for the Edwin I. Hatch Nuclear Plant, Units 1 and 2.
The ASME OM Code requires that Class 1 pressure relief valves shall be tested at least once every 5 years, with a minimum of 20% of the valves from each valve group required to be tested within any 24-month period. SNCs proposed alternative RRV12 would extend the frequency for testing all main steam safety relief valves (SRV) for each unit from once every 5 years to once every three refueling cycles (i.e., six years), as allowed by Code Case OM-17. Pursuant to 10 CFR 50.55a(z)(2), SNC is requesting NRC authorization of this alternative on the basis that compliance with the specified requirements would result in a hardship or unusual difficulty without a compensating increase in the level of quality and safety.
The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this request for alternative to the ASME Code requirements. 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 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 independent assessment regarding the acceptability of the proposed alternative 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 100 hours4.167 days <br />0.595 weeks <br />0.137 months <br /> to complete. The NRC staff expects to complete this review within 9 months, which is generally consistent with your requested
approval date of January 25, 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) 415-4032.
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