ML18193B112
| ML18193B112 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/12/2018 |
| From: | NRC |
| To: | NRC/NRO/DLSE/LB4 |
| References | |
| Download: ML18193B112 (4) | |
Text
1 Vogtle PEmails From:
Habib, Donald Sent:
Thursday, July 12, 2018 1:16 PM To:
Vogtle PEmails
Subject:
FW: Feedback on Draft License Conditions based on Public Call discussion Attachments:
RAI LAR-17-037 Feedback from Public Call (07-12).pdf From: Haggerty, Neil [1]
Sent: Thursday, July 12, 2018 11:58 AM To: Habib, Donald <Donald.Habib@nrc.gov>
Cc: Patel, Chandu <Chandu.Patel@nrc.gov>; Aughtman, Amy G. <AGAUGHTM@SOUTHERNCO.COM>; Sparkman, Wesley A. <WASPARKM@southernco.com>; Redd, Jason P. <JPREDD@southernco.com>; Hicks, Thomas E.
<X2TEHICK@southernco.com>; Amundson, Theodore Edwin <X2TAMUNS@southernco.com>; Pierce, Chuck R.
<CRPIERCE@southernco.com>
Subject:
[External_Sender] Feedback on Draft License Conditions based on Public Call discussion
- Don, We appreciate the staffs feedback on this mornings Public call. I think we made some real progress on the response to this issue.
Based on this mornings interaction, we are proposing the following changes to the revised draft license condition provided in your email on Tuesday, July 11 [ML18191A939]. Please provide this to the staff for their review. Note that we are proposing to retain the first criterion in the original license condition provided in LAR-17-037, with one minor change (construction materials to structural materials), then we would add another new criterion (either #2 or #7), that would include these 3 sub-bullets.
Also, we understand that the staff is still reviewing changes to the other Criteria in the proposed license condition from LAR-17-037, as supplemented, and look forward to reviewing the revised criteria when they are available.
Thank you, Neil Haggerty Neil Haggerty l Southern Nuclear Operating Company Nuclear Development Regulatory Affairs - VEGP 3&4 Licensing SNC-Inverness: 205.992.7047 l office: 301.874.8537 l mobile: 240.566.2442 x2nhagge@southernco.com neil.haggerty@excelservices.com This e-mail and any attachments thereto are intended only for the use by the addressee(s) named herein and may contain proprietary and confidential information. If you have received this e-mail in error, please immediately notify me by telephone and permanently delete the original and any copy of any e-mail and any printout thereof.
2
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Subject:
FW: Feedback on Draft License Conditions based on Public Call discussion Sent Date:
7/12/2018 1:16:04 PM Received Date:
7/12/2018 1:16:09 PM From:
Habib, Donald Created By:
Donald.Habib@nrc.gov Recipients:
"Vogtle PEmails" <Vogtle.PEmails@nrc.gov>
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Feedback from Public Call re: RAI LAR-17-037-2 Criterion 1 would remain as originally proposed in LAR-17-037 (except that construction would be changed to structural, as per and earlier SEB comment):
- 1. Involve design methodology or construction structural materials that deviate from a code or standard credited in the plant-specific DCD for establishing the criteria for the design or construction of a structure, system, or component (SSC) important to safety, A new criterion (2 or 7) would be added as follows:
Proposed (SNC) wording:
x Involve analysis methods or design methodology, including design codes, analytical assumptions, or structural materials, that deviate from those credited in the plant-specific DCD for critical sections, x
Result in a change to the steel-concrete (SC) module walls in the Nuclear Island or a change to the Shield Building (excluding attachments or appurtenances), including SC-to-reinforced concrete (RC) connections, x
Result in a change to the demand to capacity ratio (area of steel provided to that specified in the plant-specific DCD) of a critical section of the structure that when analyzed using local demand and actual steel values exceeds the ratio values stated in or calculated from UFSAR Section 3.8 and Appendix 3H Tables Tier 2* values for the applicable structural member, DRAFT ruction ruction at deviate from a at devia cod he he criteria for the design criteria for mportant to safety, mportant to safety, hodology, including design codes, analytica gy, including desig hat deviate from those credited in the plant from those cr
-concrete (SC) module walls concrete (SC) module walls in the Nuclea in the ng (excluding attachments or appurtenance xcluding attachments or appurtenan AF RC) connections ection,
to the demand to capacity ratio (area of ste o capacity ratio (area of ste lant ant-specific spec DCD) of a critical section of the of a critical s g local demand and actual steel values exce g local demand and actual stee RA d from UFSAR Section 3.8 and Appendix 3 d from UFSAR Section 3.8 and A RA e structural member e structural member, RA