ML19221B449
| ML19221B449 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/09/2019 |
| From: | NRC |
| To: | NRC/NRO/DLSE/LB4 |
| References | |
| Download: ML19221B449 (7) | |
Text
Vogtle PEmails From: Gleaves, Bill Sent: Friday, August 9, 2019 8:07 AM To: Leighty, Steven Cc: Vogtle PEmails
Subject:
RE: RE: RE: Vogtle LAR-19-005 Draft RAI 9696 Attachments: Vogtle LAR-19-005 Draft RAI_9696 (rev_8-1-19).pdf
- Steve, Here is the information on the clarification call:
It will be Thursday August 15th at 9:00am Call-in Information: Public Bridgeline: 888-790-9491 Passcode: 98367#
RAI clarification call on LAR 19-005, Consolidation of Structural Building ITAAC draft RAIs.
Estimated time: 9:00 - 9:30.
NRC Staff: Billy Gleaves, Mike Dudek, Ed Stutzcage, Privan Patel, Chris Welch, Jennifer Dixon-Herrity Billy William (Billy) Gleaves Senior Project Manager NRO/DLSE/Licensing Branch 2 (was Licensing Branch 4)
US Nuclear Regulatory Commission The contents of this message may be sensitive. If this message has been received in error, please delete it without reading it. Your receipt of this message is not intended to waive any applicable privilege. Do not disseminate this message without the permission of the author. Communications by this author do not represent NRC policy and are not binding on the Commission.
From: Leighty, Steven <sleighty@southernco.COM>
Sent: Wednesday, August 7, 2019 3:04 PM To: Gleaves, Bill <Bill.Gleaves@nrc.gov>
Subject:
[External_Sender] RE: RE: Vogtle LAR-19-005 Draft RAI 9696
- Billy, I received your voicemail. We understand the potential schedule issues but we would like to still have the call next week, if possible.
- Thanks, Steve Leighty l Southern Nuclear Licensing Supervisor l Vogtle 3&4 706.848.6790 l sleighty@southernco.com From: Leighty, Steven <sleighty@southernco.COM>
Sent: Tuesday, August 6, 2019 10:32 AM 1
To: Rankin, Jennivine <Jennivine.Rankin@nrc.gov>; Gleaves, Bill <Bill.Gleaves@nrc.gov>
Cc: Roberts, Kelli Anne <KROBERTS@southernco.com>; Patel, Chandu <Chandu.Patel@nrc.gov>
Subject:
[External_Sender] RE: Vogtle LAR-19-005 Draft RAI 9696 Jennie/Billy, We have reviewed the draft RAI and we would like to have a clarification call. Could we schedule the call during the public meeting next week on 8/15?
- Thanks, Steve Leighty Licensing Supervisor, Vogtle 3&4 Southern Nuclear 7825 River Road Waynesboro, GA 30830 Desk. 706.848.6790 Cell. 724.570.9412 southernnuclear.com From: Rankin, Jennivine <Jennivine.Rankin@nrc.gov>
Sent: Friday, August 2, 2019 8:03 AM To: Leighty, Steven <sleighty@southernco.COM>; Roberts, Kelli Anne <KROBERTS@southernco.com>
Cc: Patel, Chandu <Chandu.Patel@nrc.gov>; Dixon-Herrity, Jennifer <Jennifer.Dixon-Herrity@nrc.gov>; Dudek, Michael
<Michael.Dudek@nrc.gov>; Stutzcage, Edward <Edward.Stutzcage@nrc.gov>; Vogtle PEmails
<Vogtle.PEmails@nrc.gov>; Gleaves, Bill <Bill.Gleaves@nrc.gov>
Subject:
Vogtle LAR-19-005 Draft RAI 9696 EXTERNAL MAIL: Caution Opening Links or Files Steve and Kelli, Attached is our management-approved draft RAI on the LAR-19-005. The next step is for SNC to identify if it has questions or comments or, if not, to accept the draft RAI as final by informing Billy of the acceptance.
Please let Billy or myself know by Tuesday morning if a clarification call is needed.
This email is also being sent to public ADAMS capture. If there is sensitive information, please inform me ASAP so that it will prevented from public viewing.
Please let me know if you have any questions.
- Thanks, Jennie Jennie Rankin, Project Manager Licensing Branch 2 2
Division of Licensing, Siting, and Environmental Analysis Office of New Reactors 3
Hearing Identifier: Vogtle_COL_Docs_Public Email Number: 466 Mail Envelope Properties (BN7PR09MB29168841ED0367D3397F27309FD60)
Subject:
RE: RE: RE: Vogtle LAR-19-005 Draft RAI 9696 Sent Date: 8/9/2019 8:06:42 AM Received Date: 8/9/2019 8:06:46 AM From: Gleaves, Bill Created By: Bill.Gleaves@nrc.gov Recipients:
"Vogtle PEmails" <Vogtle.PEmails@nrc.gov>
Tracking Status: None "Leighty, Steven" <sleighty@southernco.COM>
Tracking Status: None Post Office: BN7PR09MB2916.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 4093 8/9/2019 8:06:46 AM Vogtle LAR-19-005 Draft RAI_9696 (rev_8-1-19).pdf 107301 image001.gif 2075 Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:
Recipients Received:
DRAFT Request for Additional Information Vogtle Nuclear Site, Units 3 and 4, Dockets 52-0025 and 52-0026 Southern Nuclear Operating Co.
Docket Nos. 52-0025 and 52-0026 Section: 14.03.08 - Radiation Protection Inspections, Tests, Analyses, and Acceptance Criteria Application Section: Tier 1
Background
In LAR-19-005, the licensee requests changes to COL Appendix C and Tier 1, Table 3.3-1, "Definition of Wall Thicknesses for Nuclear Island Buildings, Turbine Building, and Annex Building," and Table 3.3-6, "Inspections, Tests, Analyses, and Acceptance Criteria." The proposed changes include the allowance of construction deviations from the thicknesses of radiation shielding barriers and the structural wall thickness in the nuclear island structures and annex building, if the changes can be made without a "loss of shielding function" and the structures will withstand design bases loads without loss of structural integrity or safety-related function.
Issue The proposed wording in Table 3.3-1, Footnotes 15, 16, and 17, and the Table 3.3-6 ITAAC acceptance criteria for ITAAC 3.3.00.02a.i.a, 3.3.00.02a.i.b, 3.3.00.02a.i.c, 3.3.00.02a.i.d, 3.3.00.02a.ii.e, 3.3.00.02a.ii.f, and 3.3.00.04b do not provide the clarity needed to assure that the proposed changes are designed and implemented consistently. As currently proposed, the criteria for loss of shielding function are unclear with regards to radiation shielding functionality and aggregate impacts (e.g., occupational dose, public dose, environmental qualification, SSC degradation, control room dose, vital area doses, and, as applicable, equipment survivability).
Additionally, the methodologies should be consistent with those used in the design certification.
Similarly, for structures the criteria to assess the resulting structural integrity is unclear and it is indeterminate whether the applicants proposal accounts for the global impacts of all proposed changes so that the changes do not result in a loss of structural integrity or safety-related functions.
The footnotes and associated ITAAC acceptance criteria should clearly define the radiation shielding functional requirements to be met when the licensee deviates from the thicknesses and tolerances that are currently in Table 3.3-1.
For the structural reconciliation of construction deviations mentioned in footnotes 15, 16, and 17 of the LAR enclosure 3, the staff is unclear about the bases used to justify deviations from the Tier 1 values, including details on the evaluation method and acceptance criteria. The staff did not find the supporting information in Tier 2 that provides the methodology to be used; nor did the staff find the associated acceptance criteria.
Question Please clarify or revise, as appropriate, the Table 3.3-1 Footnotes 15, 16, and 17 and the acceptance criteria for ITAAC 3.3.00.02a.i.a, 3.3.00.02a.i.b, 3.3.00.02a.i.c, 3.3.00.02a.i.d, 3.3.00.02a.ii.e, 3.3.00.02a.ii.f, and 3.3.00.04b in Table 3.3-6 to provide criteria that ensures that
radiation shielding function and structural integrity remain appropriate and the facility has been constructed and will be operated in accordance with the design and all relevant requirements.
Regulatory Basis 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 2, Design Bases for Protection against Natural Phenomena, requires that SSCs important to safety shall be designed to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions.
GDC 4, Environmental and Dynamic Effects Design Bases, requires that SSCs important to safety shall be designed to accommodate the effects of and to be compatible with the environmental conditions associated with normal operation, maintenance, testing and postulated accidents, including loss-of-coolant accidents.
GDC 61, requires that the fuel storage and handling, radioactive waste, and other systems which may contain radioactivity shall be designed to assure adequate safety under normal and postulated accident conditions. These systems shall be designed (1) with a capability to permit appropriate periodic inspection and testing of components important to safety (2) with suitable shielding for radiation protection, and (3) with appropriate containment, confinement, and filtering systems.
10 CFR 52.80(a) requires that the application must contain the proposed inspections, tests, and analyses, that the licensee shall perform, and the acceptance criteria that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, the facility has been constructed and will be operated in conformity with the combined license, the provisions of the Act, and the Commission's rules and regulations.