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
{{#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


CNL-14-093
==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                  06/30/2014 Assessment


July 16, 2014 10 CFR 50, Appendix E, Section V 10 CFR 50.4 ATTN:  Document Control Desk
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.
U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001
JW!r Respectfully, Vice  Pre~ent, Nuclear Lie
 
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}}
==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}}

Revision as of 08:52, 31 October 2019

Submittal of Central Emergency Control Center - Emergency Plan Implementing Procedure Revision
ML15205A213
Person / Time
Site: Browns Ferry, Watts Bar, Sequoyah  Tennessee Valley Authority icon.png
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 06/30/2014 Assessment

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.

JW!r Respectfully, 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