Semantic search

This page or action requires JavaScript to work. Please enable JavaScript in your browser or use a browser where it is supported, so that functionality can be provided as requested. For further assistance, please have a look at the noscript help page.

Options | Search Clear all entries |

Condition

Printout selection

Options

Parameters [+]

limit:

The maximum number of results to return

offset:

The offset of the first result

link:

Show values as links

headers:

Display the headers/property names

mainlabel:

The label to give to the main page name

intro:

The text to display before the query results, if there are any

outro:

The text to display after the query results, if there are any

searchlabel:

Text for continuing the search

default:

The text to display if there are no query results

class:

An additional CSS class to set for the table

transpose:

Display table headers vertically and results horizontally

sep:

The separator between results

prefix:

Control display of namespace in printouts

Sort options

Delete

Add sorting condition

ResultCodeDebugExtra

To embed this query inline into a wiki page use the code below.

{{#ask: [[Topic::Reactor Vessel Water Level]] [[Site::Browns Ferry]]
 |?Issue date
 |?Title
 |format=table
 |limit=50
 |offset=0
 |sort=
 |order=asc
 |mainlabel=
 |searchlabel=Browns Ferry
}}

Results 1 – 50 previous 50 20 50 100 250 500 next 50

JSON CSV RSS RDF

Query log

{
    "query_string": "[[Topic::Reactor Vessel Water Level]] [[Site::Browns Ferry]]",
    "query_source": "SMWSQLStore",
    "query_time": "4.3723",
    "from_cache": false
}

	Issue date	Title
05000259/FIN-2013004-05		Reactor Vessel Water Level 1 Initiation Logic Including the Common Accident Logic Not Evaluated for Appendix R Fire Event
05000260/LER-2005-003		Reactor Protection System Actuation from Scram Discharge Volume High Level while Shutdown
05000260/LER-2009-007		Manual Scram During Removal of a Reactor Feedwater Pump from Service
05000260/LER-2009-008		Reactor Core Isolation Cooling System Inoperable Longer Than Allowed By the Plant's Technical Specifications
05000260/LER-2010-003		Reactor Scram Due to Closure of the Main Steam Isolation Valves and Subsequent Invalid RPS Scram From The Intermediate Range Monitoring System
05000296/LER-2014-003		1 of 7
CNL-14-032, Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)	28 February 2014	Second Six-Month Status Report in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
CNL-14-081, Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry	16 May 2014	Units, 1, 2 & 3, Revised Pages to Technical Specification Change TS-478-Addition of Analytical Methodologies to Technical Specification 5.6.5 and Revision of Tech Spec 2.1.1.2 in Support of ATRIUM-10 Xm Fuel Use at Browns Ferry
CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)	11 December 2014	(Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)
CNL-14-132, Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Bro	28 August 2014	Third Six-Month Status Report and Revised Overall Integrated Plan in Response to the March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events for Brown
CNL-14-166, Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)	17 February 2015	Application to Revise Technical Specifications 3.3.6.1, Table 3.3.6.1-1, Function 5.g and Bases (BFN-TS-479)
CNL-15-002, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)	6 March 2015	Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Saftey Limits (TS-499)
CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)	25 September 2015	Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)
CNL-15-073, Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.	16 September 2015	Application to Modify the Technical Specifications by Adding New Specification TS 3.3.8.3, Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal (CAS) Logic, and Unit Priority Re-Trip Logic, And.
CNL-15-187, Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..	25 September 2015	Response to NRC Request for Additional Information (RAI) Regarding Application to Revise Technical Specifications (TS) 3.3.6.1, Table 3.3.6.1-1 to Require Standby Liquid Control (SLC) System Instrumentation In..
CNL-16-078, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)	11 May 2016	Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)
CNL-16-092, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740)- Letter 5	16 June 2016	Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740)- Letter 5
CNL-16-105, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information	24 June 2016	Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 22, Responses to Requests for Additional Information
CNL-16-126, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)	24 August 2016	Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486)
CNL-16-133, Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7	15 September 2016	Response to NRC Request for Additional Information Related to License Amendment Request for Adding New Specifications to Technical Specification 3.3.8.3 (BFN-TS-486) (CAC Nos. MF6738, MF6739, and MF6740) - Letter 7
CNL-17-034, Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power Syste	17 November 2017	Application to Modify the Technical Specifications for Browns Ferry (TS-512), Sequoyah (TS-17-03), and Watts Bar (TS-17-20) to Resolve the Open Phase Issue Identified in NRC Bulletin 2012-01, Design Vulnerability in Electrical Power System.
CNL-17-085, Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels	7 July 2017	Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels
CNL-17-098, Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels	27 July 2017	Revised Response to NRC Request for Additional Information Related to TVA Fleet License Amendment Request to Adopt NEI 99-01 Revision 6 Emergency Action Levels
CNL-19-064, Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...	8 August 2019	Response to NRC Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt Technical Specifications Task Force (TSTF)-542, Reactor Pressure Vessel Water...
CNL-21-008, Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)	5 March 2021	Application to Revise Technical Specifications to Adopt TSTF-582, RPV WIC Enhancements (BFN TS-532)
CNL-21-009, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative	31 March 2022	License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505-A, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative
CNL-22-097, Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .	1 December 2022	Response to Request for Additional Information and Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide .
ENS 45282		Logic for Common Accident Signal Is Flawed for Safe Shutdown Instruction
ENS 45391		Unit 2 Manually Scrammed After Trip of an Operating Condensate Pump and Rapidly Lowering Rvwl
ENS 46881		60-Day Telephonic Notification of Invalid Primary Containment Isolation Signal Due to Maintenance
ENS 48006		Invalid System Actuation Resulting from Post Maintenance Testing
ENS 48505		60-Day Optional Telephonic Notification of Invalid Actuation of Containment Isolation Signals
ENS 48568		60-Day Telephonic Notification of an Invalid System Actuation
ENS 48587		60-Day Telephone Notification of an Invalid System Actuation
ENS 48690		Primary Containment Isolation Actuation Signal During Surveillance
ENS 49077		60 Day Report of an Invalid Primary Containment System Isolation Signal
ENS 49942		60 Day Optional Telephone Notification of an Invalid Primary Containment Isolation Signal
ENS 50565		Invalid Actuation of General Containment Isolation Signals
ENS 50658		Invalid Specified System Actuation
ENS 50754		Invalid Actuation of a General Containment Isolation Signal Affecting More than One System
ENS 53070		Invalid Actuation of a General Containment Isolation Signal Affecting More than One System
ENS 53661		Invalid Actuation of a General Containment Isolation Signal Affecting More than One System
ENS 54332		60-Day Optional Telephonic Notification of Invalid Specified System Actuation
ENS 54341		Invalid Actuation of a Signal Affecting More than One System
ENS 54697		Invalid Actuation of a General Containment Isolation Signal Affecting More than One System
ENS 55287		60-Day Telephonic Notification of Invalid Actuation of a General Containment Isolation Signal Affecting More than One System
ENS 55660		Invalid Actuation of a General Containment Isolation Signal Affecting More than One System
IR 05000226/2003025	23 April 1985	Insp Rept 50-259/85-15,50-260/85-15 & 50-296/85-15 on 850226-0325.Violations Noted:Failure to Have All Three Trains of Standby Gas Treatment Operable & to Adhere to Tech Spec 6.3.A.6
IR 05000259/1985019	3 April 1985	Enforcement Conference Meeting Repts 50-259/85-19, 50-260/85-19 & 50-296/85-19 on 850314.Areas Reviewed:Reactor Startup W/Inoperable Water Level Instruments,Failure to Perform post-maint Testing & Certain Security Violations
IR 05000259/1986040	18 February 1987	Insp Repts 50-259/86-40,50-260/86-40 & 50-296/86-40 on 861101-1231.Violations Noted:Failure to Correct Condition Adverse to Quality,Per 10CFR50,App B

Semantic search

Query log

Navigation menu

Search