|
|
| Line 13: |
Line 13: |
| | page count = 1 | | | page count = 1 |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Updated 6/11/12 WORKSHOP #3, Inspection Plan Enhancement Browns Ferry Fire Case Study You have been provided with a description of the fire that occurred at the Browns Ferry Plant in 1975. This material was extracted in its entirety from the Perspectives on Reactor Safety Course (R-800). |
| | |
| | Your TEAM assignment |
| | |
| | After reading and considering the description of the fire event, develop a list of additional inspection attributes from the incident that could be used to enhance inspection of the Emergency Diesel Generator Performance PT (PT-21M-6) considered in the previous exercises (Workshops 1 and 2). Also consider if any of the previous attributes chosen should be refocused. In other words, use the knowledge gained from this significant, historical event to enhance your inspection of the EDG surveillance test considered in Workshops 1 and 2. |
| | |
| | Prepare a presentation of your list of attributes and be ready to discuss the bases of your selections as directed by the instructor.}} |
Revision as of 01:27, 2 August 2018
|
|---|
Category:- No Document Type Applies
MONTHYEARML23215A1632023-06-0101 June 2023
Bf 2023-301 File 2B - Exam Administrative Items (Normal Release)
ML20255A0002020-09-24024 September 2020
Staff Review of Seismic Probabilistic Risk Assessment Associated with Reevaluated Seismic Hazard Implementation of the Near Term Task Force Recommendation 2.1: Seismic
ML17125A0702017-05-0505 May 2017
FAQ 16-04
ML16145A1142016-05-24024 May 2016
ASP Analysis- Reject- Browns Ferry Nuclear Plant, Unit 3, High Pressure Coolant Injection and Reactor Core Isolation Cooling Inoperable Due to No Suction Source Aligned (LER 296-2015-001)
ML15282A1682015-09-21021 September 2015
List of Regulatory Commitments
NL-15-169, Browns Ferry, Units 1, 2 and 3 - List of Regulatory Commitments2015-09-21021 September 2015
Browns Ferry, Units 1, 2 and 3 - List of Regulatory Commitments
ML15231A3642015-05-27027 May 2015
FOIA/PA-2014-0204 - Resp 1 - Final, Group a
ML15014A1602015-01-14014 January 2015
Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process
ML15014A1532015-01-14014 January 2015
Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process
ML13143A3312013-06-0606 June 2013
Operating Boiling-Water Reactor Licensees with Mark 1 and Mark 2 Containments Addresses List - Enclosure 2
ML12170B1032012-06-18018 June 2012
0772 - G105 - Conducting Inspections - Workshop #3 Scenario
ML12056A0522012-03-12012 March 2012
Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status
ML1127100332011-09-28028 September 2011
ROP Tabletop Examples and Results
ML1122005052011-08-0404 August 2011
Crop Tabletop Example Findings
ML1119901412011-07-15015 July 2011
Brown'S Ferry Unit 3, Initial On-Site Findings of the Independent Reactor Decommissioning Trust Fund Oversight Analysis
ML1119901152011-07-15015 July 2011
Brown'S Ferry Unit 1, Initial On-Site Finding of the Independent Reactor Decommissioning Trust Fund Oversight Analysis
ML1119901272011-07-0707 July 2011
Brown'S Ferry Unit 2, Initial On-Site Findings of the Independent Reactor Decommissioning Trust Fund Oversight Analysis
ML12227A7102010-09-0202 September 2010
Geris 2000 Examination Reports and Associated Records
ML1019303172010-06-0909 June 2010
Onsite Ground/Surface Water Monitoring Questionnaire for Browns Ferry
ML1010404552010-04-14014 April 2010
EN-10-018 - Issuance of Final Significance Determination and Notice of Violation, Browns Ferry, 1, 2 & 3
ML0933507512010-01-14014 January 2010
Temporary Instruction 2515/180, Managing Fatigue
ML1011605162009-10-31031 October 2009
Part 1: Previous NRC Requests for Additional Information Matrix and Text, Part 2: Browns Ferry Unit 1 - Summary of Response to Request for Additional Information, ANP-2860(NP), Rev. 2, Browns Ferry Unit 1 - Summary of Responses to Requests
ML0907108072009-03-23023 March 2009
Submittal of Request for Additional Information from ACRS to NRC on Transmittal of ACRS Members' Concerns Regarding Containment Overpressure Credit for Browns Ferry Extended Power Uprate.
ML0810104522008-04-0404 April 2008
(BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 and Round 16 Requests for Additional Information (RAI) Regarding Steam Dryer Analyses
ML0730300342007-10-25025 October 2007
Supplemental Reply to NRC Regulatory Issue Summary (RIS) 2007-17, Preparation and Scheduling of Operator Licensing Examinations
ML0732400242007-10-25025 October 2007
Examples of Max Thermal Power License Conditions
ML0713003882007-05-0202 May 2007
Enclosure 3, List of Attendees for Discussion of ORAT Inspection Results. 05/02/2007 Summary of Public Meeting with Tennessee Valley Authority, Regarding Oversight of the Browns Ferry Unit 1 Restart Project Status by the Restart Oversight P
ML0713003802007-05-0202 May 2007
Enclosure 1, List of Attendees for Browns Ferry Unit 1 Recovery Status. 05/02/2007 Summary of Public Meeting with Tennessee Valley Authority, Regarding Oversight of the Browns Ferry Unit 1 Restart Project Status by the Restart Oversight Pan
ML0527000442005-09-21021 September 2005
Attachment 10, FAQ Log 9/21/05
ML0505404642004-02-0909 February 2004
Dynamic Web Page Printout Dated 02/09/2004 Regarding Applied Violations for Nuclear Power Plants
ML18283B5501978-01-24024 January 1978
Questionnaire for Nuclear Regulatory Commission Reliability Study of Standby Diesel Generator Units
2023-06-01
[Table view] |
Text
Updated 6/11/12 WORKSHOP #3, Inspection Plan Enhancement Browns Ferry Fire Case Study You have been provided with a description of the fire that occurred at the Browns Ferry Plant in 1975. This material was extracted in its entirety from the Perspectives on Reactor Safety Course (R-800).
Your TEAM assignment
After reading and considering the description of the fire event, develop a list of additional inspection attributes from the incident that could be used to enhance inspection of the Emergency Diesel Generator Performance PT (PT-21M-6) considered in the previous exercises (Workshops 1 and 2). Also consider if any of the previous attributes chosen should be refocused. In other words, use the knowledge gained from this significant, historical event to enhance your inspection of the EDG surveillance test considered in Workshops 1 and 2.
Prepare a presentation of your list of attributes and be ready to discuss the bases of your selections as directed by the instructor.
