ML17233A005: Difference between revisions
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| number = ML17233A005 | | number = ML17233A005 | ||
| issue date = 08/18/2017 | | issue date = 08/18/2017 | ||
| title = | | title = NRR E-mail Capture - Hatch Nuclear Plant Unit 2 - Acceptance for Review of Request for Alternative RR-V-11 Regarding Main Steam SRV Test Frequency | ||
| author name = Hall R | | author name = Hall R | ||
| author affiliation = NRC/NRR/DORL/LPLII-1 | | author affiliation = NRC/NRR/DORL/LPLII-1 | ||
| addressee name = | | addressee name = Mcelroy K | ||
| addressee affiliation = Southern Nuclear Operating Co, Inc | | addressee affiliation = Southern Nuclear Operating Co, Inc | ||
| docket = 05000366 | | docket = 05000366 | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter: | {{#Wiki_filter:NRR-PMDAPEm Resource From: Hall, Randy Sent: Friday, August 18, 2017 4:46 PM To: Ken McElroy Cc: Joyce, Ryan M. (RMJOYCE@southernco.com); jjhutto@southernco.com | ||
==Subject:== | ==Subject:== | ||
Hatch Nuclear Plant Unit 2 - Acceptance | Hatch Nuclear Plant Unit 2 - Acceptance for Review of Request for Alternative RR-V-11 regarding Main Steam SRV Test Frequency (CAC No. MG0071) | ||
August 18, 2017 Mr. G. Ken McElroy Licensing Manager Southern Nuclear Operating Company | |||
Mr. G. Ken McElroy Licensing Manager Southern Nuclear Operating Company | |||
==Dear Ken,== | ==Dear Ken,== | ||
By letter dated August 3, 2017 (Agencywide Documents Access and Management System Accession No. ML17215A558), 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, Unit 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. The alternative request, RR-V-11, would allow a one-time extension of the frequency for testing certain main steam safety relief valve (SRV) main bodies from 24 to roughly 34 months, to coincide with the next Unit 2 refueling outage in February 2019. 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. | By letter dated August 3, 2017 (Agencywide Documents Access and Management System Accession No. ML17215A558), 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, Unit 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. The alternative request, RR-V-11, would allow a one-time extension of the frequency for testing certain main steam safety relief valve (SRV) main bodies from 24 to roughly 34 months, to coincide with the next Unit 2 refueling outage in February 2019. 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) | 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 | 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 8 months, which is consistent with your requested approval date of May 1, 2018. 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. | |||
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 | 1 | ||
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 8 months, which is consistent with your requested approval date of May 1, 2018. 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. | |||
Office of Nuclear Reactor Regulation USNRC (301) 415-4032 Randy.Hall@nrc.gov | 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 2 | |||
Hearing Identifier: | Hearing Identifier: NRR_PMDA Email Number: 3672 Mail Envelope Properties (Randy.Hall@nrc.gov20170818164600) | ||
==Subject:== | ==Subject:== | ||
Hatch Nuclear Plant Unit 2 - Acceptance for Review of Request for Alternative RR-V-11 regarding Main Steam SRV Test Frequency (CAC No. MG0071) | Hatch Nuclear Plant Unit 2 - Acceptance for Review of Request for Alternative RR-V-11 regarding Main Steam SRV Test Frequency (CAC No. MG0071) | ||
Tracking Status: None Post Office: | Sent Date: 8/18/2017 4:46:01 PM Received Date: 8/18/2017 4:46:00 PM From: Hall, Randy Created By: Randy.Hall@nrc.gov Recipients: | ||
"Joyce, Ryan M. (RMJOYCE@southernco.com)" <RMJOYCE@southernco.com> | |||
Options | Tracking Status: None "jjhutto@southernco.com" <jjhutto@southernco.com> | ||
Tracking Status: None "Ken McElroy" <gkmcelro@southernco.com> | |||
Tracking Status: None Post Office: | |||
Files Size Date & Time MESSAGE 3724 8/18/2017 4:46:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: | |||
Recipients Received:}} |
Latest revision as of 20:03, 8 March 2020
ML17233A005 | |
Person / Time | |
---|---|
Site: | Hatch ![]() |
Issue date: | 08/18/2017 |
From: | Randy Hall Plant Licensing Branch II |
To: | Mcelroy K Southern Nuclear Operating Co |
References | |
MG0071 | |
Download: ML17233A005 (3) | |
Text
NRR-PMDAPEm Resource From: Hall, Randy Sent: Friday, August 18, 2017 4:46 PM To: Ken McElroy Cc: Joyce, Ryan M. (RMJOYCE@southernco.com); jjhutto@southernco.com
Subject:
Hatch Nuclear Plant Unit 2 - Acceptance for Review of Request for Alternative RR-V-11 regarding Main Steam SRV Test Frequency (CAC No. MG0071)
August 18, 2017 Mr. G. Ken McElroy Licensing Manager Southern Nuclear Operating Company
Dear Ken,
By letter dated August 3, 2017 (Agencywide Documents Access and Management System Accession No. ML17215A558), 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, Unit 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. The alternative request, RR-V-11, would allow a one-time extension of the frequency for testing certain main steam safety relief valve (SRV) main bodies from 24 to roughly 34 months, to coincide with the next Unit 2 refueling outage in February 2019. 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 8 months, which is consistent with your requested approval date of May 1, 2018. 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.
1
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 2
Hearing Identifier: NRR_PMDA Email Number: 3672 Mail Envelope Properties (Randy.Hall@nrc.gov20170818164600)
Subject:
Hatch Nuclear Plant Unit 2 - Acceptance for Review of Request for Alternative RR-V-11 regarding Main Steam SRV Test Frequency (CAC No. MG0071)
Sent Date: 8/18/2017 4:46:01 PM Received Date: 8/18/2017 4:46:00 PM From: Hall, Randy Created By: Randy.Hall@nrc.gov Recipients:
"Joyce, Ryan M. (RMJOYCE@southernco.com)" <RMJOYCE@southernco.com>
Tracking Status: None "jjhutto@southernco.com" <jjhutto@southernco.com>
Tracking Status: None "Ken McElroy" <gkmcelro@southernco.com>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 3724 8/18/2017 4:46:00 PM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received: