CNL-13-110, Central Emergency Control Center - Revision 20 to Emergency Plan Implementing Procedure Revision CECC EPIP-19, Post Accident Fuel Damage Assessment

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Central Emergency Control Center - Revision 20 to Emergency Plan Implementing Procedure Revision CECC EPIP-19, Post Accident Fuel Damage Assessment
ML15205A191
Person / Time
Site: Browns Ferry, Watts Bar, Sequoyah  Tennessee Valley Authority icon.png
Issue date: 11/08/2013
From: James Shea
Tennessee Valley Authority
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CNL-13-110
Download: ML15205A191 (2)


Text

Tennessee Valley Authority, 1101 Market Street, Chattanooga, Tennessee 37402 CNL-13-110 November 8, 2013 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 10 CFR Part 50, Appendix E, Section V, this submittal provides the revised Central Emergency Control Center (CECC) Emergency Plan Implementing Procedure (EPIP) as listed below.

EPIP Revision Title Effective Date CECC EPIP-19 20 Post Accident Fuel Damage 10/11/2013 Assessment provides a summary of the changes and the analysis performed that concluded that following implementation of the changes, the CECC EPIP continues to comply with the requirements of 10 CFR 50.47 and 10 CFR 50, Appendix E. The changes do not constitute a reduction in effectiveness to the Radiological Emergency Plan (REP) or its implementing procedures. Enclosure 2 provides a copy of the revised EPIP.

Printed on recycled paper

U.S. Nuclear Regulatory Commission Page 2 November 8, 2013 There are no new regulatory commitments in this letter. If you have any questions regarding this submittal, please contact E. D. Schrull at (423) 751-3850.

Respe ly, ice resident, Nuclear Licensing

Enclosures:

1. Summary of Changes and Analysis
2. Central Emergency Control Center (CECC), Emergency Plan Implementing Procedure (EPIP) Revision 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