ML17255A026: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| (2 intermediate revisions by the same user not shown) | |||
| Line 2: | Line 2: | ||
| number = ML17255A026 | | number = ML17255A026 | ||
| issue date = 09/11/2017 | | issue date = 09/11/2017 | ||
| title = Acceptance for Review - Licensing Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) (MG0113, MG0114, and MG0115)) | | title = NRR E-mail Capture - Browns Ferry Units 1, 2, and 3 - Acceptance for Review - Licensing Application to Revise Technical Specification 5.5.12 Primary Containment Leakage Rate Testing Program (BFN-TS-497) (MG0113, MG0114, and MG0115)) | ||
| author name = Saba F | | author name = Saba F | ||
| author affiliation = NRC/NRR/DORL/LPLII-2 | | author affiliation = NRC/NRR/DORL/LPLII-2 | ||
| Line 25: | Line 25: | ||
LICENSING APPLICATION TO REVISE TECHNICAL SPECIFICATION 5.5.12 PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM (BFN-TS-497) (MG0113, MG0114, and MG0115)) | LICENSING APPLICATION TO REVISE TECHNICAL SPECIFICATION 5.5.12 PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM (BFN-TS-497) (MG0113, MG0114, and MG0115)) | ||
Importance: High | Importance: High | ||
: Gordon, By letter dated August 15, 2017 (Agencywide Documents Access and Management System Accession No. | : Gordon, By letter dated August 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17228A490), the Tennessee Valley Authority submitted a license amendment for Browns Ferry Units 1, 2, and 3 (Browns Ferry). The proposed amendment would revise Browns Ferrys Technical Specification 5.5.12 Primary Containment Leakage Rate Testing [ILRT] Program, by adopting Nuclear Energy Institute (NEI) 94-01, Revision 3-A, Industry Guideline for Implementing Performance-Based Option of Title 10 of the Code of Federal Regulations (10 CFR) | ||
ML17228A490), the Tennessee Valley Authority submitted a license amendment for Browns Ferry Units 1, 2, and 3 (Browns Ferry). The proposed amendment would revise Browns Ferrys Technical Specification 5.5.12 Primary Containment Leakage Rate Testing [ILRT] Program, by adopting Nuclear Energy Institute (NEI) 94-01, Revision 3-A, Industry Guideline for Implementing Performance-Based Option of Title 10 of the Code of Federal Regulations (10 CFR) | |||
Part 50, Appendix J, as the implementation document for the performance-based Option B of 10 CFR Part 50, Appendix J. The proposed changes would allow the Type A containment ILRT to be performed within 15 years from the last test on each unit. | Part 50, Appendix J, as the implementation document for the performance-based Option B of 10 CFR Part 50, Appendix J. The proposed changes would allow the Type A containment ILRT to be performed within 15 years from the last test on each unit. | ||
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment 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 purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment 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. | ||
Consistent with 10 CFR 50.90, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | Consistent with 10 CFR 50.90, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | ||
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 850 hours to complete. The NRC staff expects to complete this review by October 31, 2018, as requested in the August 15, 2017 letter. 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. | Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately [[estimated NRC review hours::850 hours]] to complete. The NRC staff expects to complete this review by October 31, 2018, as requested in the August 15, 2017 letter. 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. | 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 301-415-1447. | If you have any questions, please contact me at 301-415-1447. | ||
Latest revision as of 19:21, 8 March 2020
| ML17255A026 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 09/11/2017 |
| From: | Farideh Saba Plant Licensing Branch II |
| To: | Gerald Williams Tennessee Valley Authority |
| References | |
| MG0113, MG0114, MG0115 | |
| Download: ML17255A026 (3) | |
Text
NRR-PMDAPEm Resource From: Saba, Farideh Sent: Monday, September 11, 2017 4:25 PM To: Williams, Gordon Robert (grwilliams1@tva.gov); Hammargren, Benjamin John (bjhammargren@tva.gov)
Cc: Schrull, Edward Dustin (edschrull@tva.gov); Shoop, Undine; Hon, Andrew; Jordan, Natreon; Clayton, Beverly
Subject:
FW: Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Acceptance for Review -
LICENSING APPLICATION TO REVISE TECHNICAL SPECIFICATION 5.5.12 PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM (BFN-TS-497) (MG0113, MG0114, and MG0115))
Importance: High
- Gordon, By letter dated August 15, 2017 (Agencywide Documents Access and Management System Accession No. ML17228A490), the Tennessee Valley Authority submitted a license amendment for Browns Ferry Units 1, 2, and 3 (Browns Ferry). The proposed amendment would revise Browns Ferrys Technical Specification 5.5.12 Primary Containment Leakage Rate Testing [ILRT] Program, by adopting Nuclear Energy Institute (NEI) 94-01, Revision 3-A, Industry Guideline for Implementing Performance-Based Option of Title 10 of the Code of Federal Regulations (10 CFR)
Part 50, Appendix J, as the implementation document for the performance-based Option B of 10 CFR Part 50, Appendix J. The proposed changes would allow the Type A containment ILRT to be performed within 15 years from the last test on each unit.
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment 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.
Consistent with 10 CFR 50.90, an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 850 hours35.417 days <br />5.06 weeks <br />1.164 months <br /> to complete. The NRC staff expects to complete this review by October 31, 2018, as requested in the August 15, 2017 letter. 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 301-415-1447.
- Thanks, 1
Farideh Farideh E. Saba, P.E.
Senior Project Manager NRC/ADRO/NRR/DORL 301-415-1447 Mail Stop O-8B01A Farideh.Saba@NRC.GOV 2
Hearing Identifier: NRR_PMDA Email Number: 3721 Mail Envelope Properties (Farideh.Saba@nrc.gov20170911162500)
Subject:
FW: Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Acceptance for Review -
LICENSING APPLICATION TO REVISE TECHNICAL SPECIFICATION 5.5.12 PRIMARY CONTAINMENT LEAKAGE RATE TESTING PROGRAM (BFN-TS-497) (MG0113, MG0114, and MG0115))
Sent Date: 9/11/2017 4:25:20 PM Received Date: 9/11/2017 4:25:00 PM From: Saba, Farideh Created By: Farideh.Saba@nrc.gov Recipients:
"Schrull, Edward Dustin (edschrull@tva.gov)" <edschrull@tva.gov>
Tracking Status: None "Shoop, Undine" <Undine.Shoop@nrc.gov>
Tracking Status: None "Hon, Andrew" <Andrew.Hon@nrc.gov>
Tracking Status: None "Jordan, Natreon" <Natreon.Jordan@nrc.gov>
Tracking Status: None "Clayton, Beverly" <Beverly.Clayton@nrc.gov>
Tracking Status: None "Williams, Gordon Robert (grwilliams1@tva.gov)" <grwilliams1@tva.gov>
Tracking Status: None "Hammargren, Benjamin John (bjhammargren@tva.gov)" <bjhammargren@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 2971 9/11/2017 4:25:00 PM Options Priority: High Return Notification: No Reply Requested: Yes Sensitivity: Normal Expiration Date:
Recipients Received: