ML18103A215: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 1: Line 1:
{{Adams
#REDIRECT [[NL-18-055, Browns Ferry Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar Units 1 and 2 - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions]]
| number = ML18103A215
| issue date = 04/11/2018
| title = Browns Ferry Units 1, 2, and 3; Sequoyah, Units 1 and 2; Watts Bar Units 1 and 2 - Central Emergency Control Center Emergency Plan Implementing Procedure Revisions
| author name = Shea J W
| author affiliation = Tennessee Valley Authority
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NMSS, NRC/NRR
| docket = 05000259, 05000260, 05000296, 05000327, 05000328, 05000390, 05000391, 07200034, 07200052, 07201048
| license number = DPR-033, DPR-052, DPR-068, DPR-077, DPR-079, NPF-090, NPF-096
| contact person =
| case reference number = CNL-18-055
| document type = Emergency Preparedness-Emergency Plan Implementing Procedures, Letter
| page count = 2
}}
 
=Text=
{{#Wiki_filter:Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-18-0 55 April 11, 2018  10 CFR 50.54(q) 10 CFR 72.44(f)
ATTN:  Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
-0001  Browns Ferry Nuclear Plant, Units 1, 2, and 3 Renewed Facility Operating License Nos. DPR
-33, DPR-52, and DPR
-68 NRC Docket Nos. 50
-259, 50-260, 50-296, and 72
-052  Sequoyah Nuclear Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR
-77 and DPR
-79 NRC Docket Nos. 50
-327, 50-328, and 72
-034  Watts Bar Nuclear Plant, Units 1 and 2 Facility Operating License Nos. NPF
-90 and NPF
-96 NRC Docket Nos. 50
-390, 50-391, and 72
-1048 
 
==SUBJECT:==
TENNESSEE VALLEY AUTHORITY - CENTRAL EMERGENCY CONTROL CENTER EMERGENCY PLAN IMPLEMENTING PROCEDURE REVISION S  In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) 50.54(q) and 10 CFR 72.44(f), Tennessee Valley Authority (TVA) is submitting a description of changes to the TVA Radiological Emergency Plan (REP). The affected document s are the Central Emergency Control Center (CECC)
Emergency Plan Implementing Procedure s (EPIP) named below. Document Revision Title Effective Date CECC EPIP-9 58  Emergency Environmental Radiological Monitoring Procedures 4/6/2018 U.S. Nuclear Regulatory Commission CNL-18-055 Page 2 April 11, 2018 Description of Changes and Summary of Analysis CECC EPIP-9 was revised to clarify data fields for logging field team readings, to clarify that the Scintrex tritium monitors apply to the inventory requirements for the Watts Bar Nuclear Plant only, and to update instructions for use of the environmental monitoring van global positioning system (GPS) units. Other minor/editorial changes were also made as part of the revision.
These changes were evaluated in accordance with 10 CFR 50.54(q)(3).
TVA determined that the changes do not reduce the effectiveness of the TVA REP. The TVA REP, as revised , continues to meet the requirements in Appendix E to 10 CFR 50 and the planning standards of 10 CFR 50.47(b).
There are no new regulatory comm i tments in this letter. If you have any questions regarding this submittal, please contact Ed Schrull at (423) 751-3850 . cc: . Shea President , Nuclear Regulatory Affairs and Support Services NRC Regional Administrator
-Region II NRC Senior Resident Inspector
-Browns Ferry Nuclear Plant NRC Senior Resident Inspector
-Sequoyah Nuclear Plant NRC Senior Resident Inspector
-Watts Bar Nuclear Plant NRR Project Manager -Browns Ferry Nuclear Plant NRR Project Manager -Sequoyah Nuclear Plant NRR Project Manager -Watts Bar Nuclear Plant NRC Director -Division of Spent Fuel Management, NMSS}}

Revision as of 23:46, 11 July 2018

Redirect to:

Retrieved from "https://kanterella.com/w/index.php?title=ML18103A215&oldid=878033"