ML16334A315: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 15: | Line 15: | ||
=Text= | =Text= | ||
{{#Wiki_filter:Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 November 28, 2016 | {{#Wiki_filter:Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 November 28, 2016 ATTN: | ||
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 10CFR50.4 10 CFR 50.46 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 | |||
==Subject:== | ==Subject:== | ||
| Line 25: | Line 26: | ||
This submittal satisfies the annual reporting requirement of 10 CFR 50.46(a)(3)(H). | This submittal satisfies the annual reporting requirement of 10 CFR 50.46(a)(3)(H). | ||
There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mike McBrearty at (423) 843-7170. | There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mike McBrearty at (423) 843-7170. | ||
Respectfully, Gregory A. Boerschig | Respectfully, | ||
^-^ | |||
Gregory A. Boerschig | |||
\\V SiteVice President (Interim)0 Sequoyah Nuclear Plant printed on recycled paper}} | |||
Latest revision as of 18:57, 9 January 2025
| ML16334A315 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 11/28/2016 |
| From: | Boerschig G Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16334A315 (1) | |
Text
Tennessee Valley Authority, Sequoyah Nuclear Plant, P.O. Box 2000, Soddy Daisy, Tennessee 37384 November 28, 2016 ATTN:
Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 10CFR50.4 10 CFR 50.46 Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328
Subject:
10 CFR 50.46 Annual Report for Sequoyah Nuclear Plant, Units 1 and 2
Reference:
TVA letter to NRC "10 CFR 50.46 Combined Annual Report for Sequoyah Nuclear Plant, Units 1 and 2" dated November 26, 2015 [ML15336A940]
The purpose of this letter is to provide the current status of the calculated peak cladding temperature (PCT) for the Sequoyah Nuclear Plant emergency core cooling system (ECCS) evaluation model. There have been no changes to the evaluation model or the calculated PCT since the submittal of the referenced 2015 Annual Report.
This submittal satisfies the annual reporting requirement of 10 CFR 50.46(a)(3)(H).
There are no regulatory commitments associated with this submittal. Should you have any questions, please contact Mike McBrearty at (423) 843-7170.
Respectfully,
^-^
Gregory A. Boerschig
\\V SiteVice President (Interim)0 Sequoyah Nuclear Plant printed on recycled paper