ML16273A466
| ML16273A466 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  (DPR-033, DPR-052, DPR-068) |
| Issue date: | 09/29/2016 |
| From: | Bono S Tennessee Valley Authority |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
| References | |
| EPIP-7, Rev.34 | |
| Download: ML16273A466 (5) | |
Text
Tennessee Valley Authority, Post Office Box 2000, Decatur, Alabama 35609-2000 September 29, 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 (1 0 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)-7, Activation and Operation of the Operations Support Center (OSC), Revision 34. 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 September 29, 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 Nuclear Plant EPIP-7, Activation and Operation of the Operations Support Center (OSC), Revision 34 Affected Description of Changes Document Description of Analysis BFN EPIP-7, Removed all instances of the The proposed change does not change any of the Revision 34 requirement to card into an processes, methods, or requirements of performing accountability card reader in the initial Assembly and Accountability in accordance with the actions of an activation of the Emergency plan. This change does not remove the Emergency Response Organization capability to account for all emergency responders onsite (ERO). The following steps will be within 30 minutes of the start of an emergency, or at any affected by this change:
other point in the emergency, and account for all onsite individuals continuously thereafter. They will be accounted Appendix E, Step 5.0 for via emergency facility sign-in rosters/boards or the exit Appendix L, Step 5.0 turnstile gate records (non-emergency responders) during Appendix P, Steps 3.0-5.0 the initial stages of an activation of the ERO. Therefore, this proposed change continues to comply with the The removal of step 3.0 (Revision 33) requirements.
requires steps 4.0-6.0 (Revision 33) to be renumbered to Steps 3.0-5.0 The proposed change is not a reduction in the (Revision 34).
effectiveness of the emergency plan, because upon initiation of the Assembly and Accountability process in Carding into an accountability card accordance with EPIP-8, all instances of carding into the reader in the initial stages of an accountability card readers prior to the initiation of the activation of the ERO is unnecessary.
system become redundant. Design Change Notice (DCN)
In previous revisions of EPIP-7, it was 69733 tracked an upgrade of the Site Security computer a step that was performed as part of system that included a feature that clears all of the the position checklists contained in the accountability readers onsite upon initiation of Assembly document. EPIP-7, Revision 31 and Accountability. This requires all ERO members to card included a change that removed this into the appropriate accountability reader upon hearing the requirement from the checklists and Accountability/Evacuation siren, PA announcement, or added instruction to "card into the direction from Site Security to perform required actions for accountability reader upon notification Assembly and Accountability. Therefore, carding into an by; public address (PA) accountability reader before the initiation of Assembly and announcement, assembly and Accountability process is unnecessary. Additionally, accountability sirens, or advice of accountability rosters and sign in boards are available for Nuclear Security personnel" to the all of Browns Ferry Nuclear Plant's emergency response notes box at the beginning of each facilities, and the requirement for ERO personnel to sign in checklist. This change was made as a on an accountability roster and sign in board (Operations result of an upgrade in the Site Support Center (OSC) and Technical Support Center Security computer system. The (TSC)) upon activation of the ERO remains unchanged.
upgrade included a change to the Assembly and Accountability process.
The change does not constitute a reduction in In the event of an initiation of the effectiveness of the REP.
Assembly and Accountability process, the card readers are cleared and any information transmitted via the card reader prior to the initiation of the system is lost. Therefore, all emergency response personnel would be required to card into the accountability reader a second time.
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Summary of Changes and Analysis for Browns Ferry Nuclear Plant EPIP-7, Activation and Operation of the Operations Support Center (OSC}, Revision 34 Affected Description of Changes and Analysis Document BFN EPIP-7, The following editorial or typographical changes were made:
Revision 34 Section 2.2-Added "Procedure" to the title of EPIP-16 to ensure the title is complete and accurate Section 2.2-Removed spaces around dashes in list Section 2.2-Added, BFN EPIP-10, "Medical Emergency Procedure," and BFN EPIP-8, "Personnel Accountability and Evacuation" Removed the position title from the identification step in Appendices B-X Added a period to the end of the following steps:
0 Main Body, Step 3.4.F 0
Appendix B, Step 3.0 (including all bulleted list items) 0 Appendix B, Step 9.0, Emergency Announcement 0
Appendix P, Step 4.0 0
Appendix P, Operational Responsibilities, first bullet 0
Appendix W, Operational Responsibilities, second bullet Changed the following phone numbers:
0 Appendix D, Step 6.0-From "extension 7839" to "729-7839" and "extension 751-1700" to "1-423-751-1700" 0
Appendix F, Step 4.0-From "ext. 101" to "ext. 7101 "
0 Appendix J, Step 4.0-From "extension 2244" to "729-2244" 0
Appendix U, Step 4.0-From "(3766)" to "(729-3766)"
Appendix D, Operational Responsibilities-Replaced "SCBAs" with "Self Contained Breathing Apparatus (SCBA)" in first bullet Appendix F, Step 6.0-Moved "(EOI Activities)" inside period Replaced "Verify" with "Ensure" in the following steps to align with the Tennessee Valley Authority Writer's Manual:
0 Appendix B, Steps 3.0 and 8.0 0
Appendix J, Step 3.0 0
Appendix K, Step 5.0 0
Appendix L, Step 7.0 Appendix K, Operational Responsibilities-Added dash to "EPI P-1 O" and title of EPI P-10 to second bullet Appendix K, Operational Responsibilities-Replaced "OSC Fire Protection Manager" with "OSC Fire Operations Briefer" in third bullet to ensure consistency with the actual title of the position Appendix L, Operational Responsibilities-Replaced "provides" with "provide" in fourth bullet Replaced "OSC RP Manager" with "OSC RP Supervisor" in the following steps:
0 Appendix R, Step 3.0 0
Appendix V, Step 5.0 0
Appendix X, Step 4.0 Appendix U, Operational Responsibilities, second bullet-Replaced "TSC Maintenance manager" with "TSC Maintenance Manager" Page 2 of 2