ML16302A329
| ML16302A329 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/28/2016 |
| From: | Bono S Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML16302A329 (5) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 October 28, 2016 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 Browns Ferry Nuclear Plant, Units 1, 2, and 3 10 CFR 50.4 10 CFR 50.54(q) 10 CFR 50, Appendix E 10 CFR 72.44(f)
Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68 NRC Docket Nos. 50-259, 50-260, 50-296, and 72-052
Subject:
Emergency Plan Implementing Procedure Revision In accordance with the requirements of Title 10 of the Code of Federal Regulations (10 CFR) Part 50.54(q), 10 CFR Part 50, Appendix E, Section V, and 10 CFR 72.44(f).
The enclosure provides a summary of the changes and analysis for Browns Ferry Nuclear Plant Emergency Plan Implementing Procedure (EPIP)-6, Activation and Operation of the Technical Support Center (TSC), Revision 38. This enclosure contains both editorial/typographical revisions, as well as non-editorial/typographical substantive revisions, which require an effectiveness evaluation. The evaluation determined the EPIP revision did not reduce the effectiveness, or change or decrease any function or element of the Tennessee Valley Authority Nuclear Power Group Radiological Emergency Plan.
U.S. Nuclear Regulatory Commission Page 2 October 28, 2016 There are no new regulatory commitments in this letter. If you have any questions regarding this EPIP revision, please contact B. F. Tidwell at (256) 729-3666.
Enclosure:
Summary of Changes and Analysis for Browns Ferry Nuclear Plant Emergency Plan Implementing Procedure cc (Enclosures):
NRC Regional Administrator - Region II NRC Senior Resident Inspector - Browns Ferry Nuclear Plant Director, Division of Spent Fuel Management, Office of Nuclear Material Safety and Safeguards
Enclosure Tennessee Valley Authority Browns Ferry Nuclear Plant Units 1, 2, and 3 Summary of Changes and Analysis for Browns Ferry Nuclear Plant Emergency Plan Implementing Procedure (See Enclosed)
Summary of Changes and Analysis for Browns Ferry EPIP-6, Activation and Operation of the Technical Support Center (TSC), Revision 38 Affected Description of Non-Editorial Changes Document Effectiveness Evaluation Changed the Notification of the NRC table in The changes evaluated do not reduce the site's Appendix J to improve the usability of the table in ability to make any of the notifications. The the event of an emergency that affects multiple changes do have the potential for reducing t he units at the site and be more consistent with NRC possibility of the NRC needing to request the Worksheets. The following changes were:
information that will now be provided by the
"(s)" after affected unit
" Notification of NRC" table. The additional corrected spelling of Contact information included in the form is readily added unit specific Power/Mode Before available using either the Integrated Computer BFN EPIP-6, added unit specific Power/Mode After System or control room instrumentation; Revision 38 Currently, there is no way of documenting an therefore, the timeliness of filling out the form will emergency t hat affects multiple units at Browns not be negatively impacted. Because of the Ferry Nuclear Plant (BFN) on the "NRC EVENT additional information that will be included on the NOTIFICATION WORKSHEET" table in EPIP-6, form, it can be reasonably concluded that the Appendix J, NRC Coordinator Checklist. The changes being evaluated here are an increase in changes to the table provide a means to ensure effectiveness of the emergency plan. Therefore, it that all units affected by the emergency are is concluded that the changes are not a reduction included on the table.
in effectiveness of the BFN Radiological Emergency Plan.
Affected Description of Editorial/Typographical Changes Document The following editorial or typographical changes were made:
Section 2.2 - Removed spaces around dashes in list.
Section 3.5.A - Removed underline from Appendix Y.
Removed additional position identifier in Appendices B-U. Having the title of the position being assumed in this step is redundant because the title of the position is contained in the header for t he appendices. Removal of the position title from this step does not remove or transfer any emergency response assignments or responsibilities.
Appendix B, Step 7.0 - Corrected Plant Public Address (PA) Extension from "687" to "7-687."
Appendix B, Operational Responsibilities - Corrected bullet 1 appendix reference for A-D from BFN EPIP-6, "Appendix C" to "Appendix E."
Appendix B, Operational Responsibilities - Corrected bullet 13 step 1 appendix reference from Revision 38 "Appendix C" to "Appendix E." Also removed underlining from Appendix E and TWO HOURS.
Appendix B, Operational Responsibilities - Added bullet 12 to state, "Discuss invoking 50.54x, when applicable, and make an announcement that 50.54x has been invoked."
Appendix C - Changed all instances of "OSC Operations Manager" to "OSC Operations Briefer."
Appendix D, Operational Responsibilities - Combined bullets 4 and 5 as it is all one step.
Appendix G, Step 5.0 - Replaced, "Confirm the Emergency Data Information System is in operation,"
with, " Log into the ERN Multi Unit (EMU) from the EP SharePoint using lookup for both t he username and password."
Appendix G, Step 6.0 - Removed extra space between "to support."
Appendix G, Operational Responsibilities - Combined bullets 4 and 5 as it is all one step.
Page 1of 2
Affected Summary of Changes and Analysis for Browns Ferry EPIP-6, Activation and Operation of the Technical Support Center (TSC), Revision 38 Document Description of Editorial/Typographical Changes Appendix H, Step 10.0 - Corrected spelling from "his" to "is."
Appendix I - Removed the third bullet in the "NOTES" box which stated, "The EP Manager (at 729-3777) may be notified of activation/operation issues."
Appendix I, Step 5.0 - Corrected EP Manager extension from "3777" to "729-3777."
Appendix I, Operational Responsibilities - Added bullet 3 that states, "Notify the OSC Clerk, OSC Staging Area manager, TSC TAT Leader, and CECC EDO of the time of upcoming SED briefings."
Appendix J, Operational Responsibilities - Added, "(with higher frequency during station blackout)"
to bullet 2.
Appendix K - Corrected Operations bridge number to "7101." The 102, listen only, is no longer in service. It has been replaced with the 7101 bridge line.
Appendix N - Corrected Operations communication bridge number to "7101."
Appendix R - Corrected Operations communication bridge number to "7101."
Appendix U, Operational Responsibilities - Added, "If copiers and fax machines do not work, give the original copy of the Plant Parameter Data Sheets to the Technical Assessment Manager (TAM)," to bullet7.
Appendix V, Note (2) - Corrected spelling from "check" to "checked."
Appendix W - Added a space for the unit designator.
Appendix X - Added a space to document procedure driven requests from other departments.
Page 2 of 2