CNL-14-093, Submittal of Central Emergency Control Center - Emergency Plan Implementing Procedure Revision: Difference between revisions
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{{#Wiki_filter:L44 140716 001 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-093 July 16, 2014 10 CFR 50, Appendix E, Section V 10 CFR 50.4 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, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 | {{#Wiki_filter:L44 140716 001 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-093 July 16, 2014 10 CFR 50, Appendix E, Section V 10 CFR 50.4 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, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390 | ||
==Subject:== | ==Subject:== | ||
Central Emergency Control Center - Emergency Plan Implementing Procedure Revision In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) | Central Emergency Control Center - Emergency Plan Implementing Procedure Revision In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) | ||
Part 50, Appendix E, Section V, this submittal provides the revised Central Emergency Control Center (CECC) Emergency Plan Implementing Procedure (EPIP) listed below. | Part 50, Appendix E, Section V, this submittal provides the revised Central Emergency Control Center (CECC) Emergency Plan Implementing Procedure (EPIP) listed below. | ||
EPIP | EPIP Revision Title Effective Date CECC EPIP-19 21 Post Accident Fuel Damage Assessment 06/30/2014 | ||
U.S. Nuclear Regulatory Commission Page 2 July 16, 2014 | U.S. Nuclear Regulatory Commission Page 2 July 16, 2014 provides a summary of the changes and the analysis performed that concluded the changes do not affect the outcome, results, functions, processes, responsibilities, or requirements of the performance of the EPIP. Enclosure 2 provides a copy of the revised EPIP. | ||
There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact Edward D. Schrull at (423) 751-3850. | There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact Edward D. Schrull at (423) 751-3850. | ||
JW!r | Respectfully, JW!r Vice Pre~ent, Nuclear Lie | ||
==Enclosures:== | ==Enclosures:== | ||
: 1. Summary of Changes and Analysis | : 1. Summary of Changes and Analysis | ||
: 2. Central Emergency Control Center (CECC), Emergency Plan Implementing Procedure (EPIP) 19, Revision 21 cc (Enclosures): | : 2. Central Emergency Control Center (CECC), Emergency Plan Implementing Procedure (EPIP) 19, Revision 21 cc (Enclosures): | ||
NRC | 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 Unit 1}} | ||
Latest revision as of 10:19, 10 January 2025
| ML15205A213 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry, Watts Bar, Sequoyah  |
| Issue date: | 07/16/2014 |
| From: | James Shea Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CNL-14-093 | |
| Download: ML15205A213 (2) | |
Text
L44 140716 001 Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-14-093 July 16, 2014 10 CFR 50, Appendix E, Section V 10 CFR 50.4 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, and 50-296 Sequoyah Nuclear Plant, Units 1 and 2 Facility Operating License Nos. DPR-77 and DPR-79 NRC Docket Nos. 50-327 and 50-328 Watts Bar Nuclear Plant, Unit 1 Facility Operating License No. NPF-90 NRC Docket No. 50-390
Subject:
Central Emergency Control Center - Emergency Plan Implementing Procedure Revision In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR)
Part 50, Appendix E,Section V, this submittal provides the revised Central Emergency Control Center (CECC) Emergency Plan Implementing Procedure (EPIP) listed below.
EPIP Revision Title Effective Date CECC EPIP-19 21 Post Accident Fuel Damage Assessment 06/30/2014
U.S. Nuclear Regulatory Commission Page 2 July 16, 2014 provides a summary of the changes and the analysis performed that concluded the changes do not affect the outcome, results, functions, processes, responsibilities, or requirements of the performance of the EPIP. Enclosure 2 provides a copy of the revised EPIP.
There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact Edward D. Schrull at (423) 751-3850.
Respectfully, JW!r Vice Pre~ent, Nuclear Lie
Enclosures:
- 1. Summary of Changes and Analysis
- 2. Central Emergency Control Center (CECC), Emergency Plan Implementing Procedure (EPIP) 19, Revision 21 cc (Enclosures):
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 Unit 1