Letter Sequence Request |
---|
|
|
MONTHYEARML1015901102002-09-25025 September 2002 Drawing, Browns Ferry Electrical Distribution System. Project stage: Other ML1015901082010-05-28028 May 2010 Technical Specification Change - TS-468 - Responses to Request for Additional Information Regarding Extending Completion Times for Emergency Diesel Generators Project stage: Response to RAI ML1026603282010-09-27027 September 2010 Notice of Meeting by Teleconference with Tennessee Valley Authority Regarding Browns Ferry Extension for Diesel Completion Time Request (TAC Nos. ME3423, ME3424, and ME3425) (TS-468) Project stage: Meeting ML1031301532010-11-10010 November 2010 Summary of Meeting Regarding Extension of Allowed Outage Time for Emergency Diesel Generators Project stage: Meeting ML1018303592010-11-18018 November 2010 June 29, 2010 Meeting Handouts Project stage: Request ML1018301132010-11-18018 November 2010 Electrical Distribution System Project stage: Request ML1018303502010-11-18018 November 2010 Meeting Handouts, Sample TSs Pages Project stage: Request 2010-11-18
[Table View] |
|
---|
Category:Slides and Viewgraphs
MONTHYEARML24032A2752024-02-0707 February 2024 Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0332023-05-11011 May 2023 NRC Presentation Browns Ferry Subsequent License Renewal Pre-application Meeting, Environmental Overview ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23130A0302023-05-10010 May 2023 TVA Presentation Browns Ferry Nuclear Plant Subsequent License Renewal License Application Environmental Report ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21250A3012021-09-0707 September 2021 TVA Slides for September 7, 2021, Presubmittal Meeting to Discuss Planned Browns Ferry TSTF-505 License Amendment Request ML21152A1872021-06-0101 June 2021 TVA Slides for June 1, 2021, Presubmittal Meeting to Discuss Planned Control Bay Chiller Cross-Tie License Amendment Request ML21096A1002021-04-0606 April 2021 Annual Assessments ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20156A2812020-06-0808 June 2020 TVA Slides for June 8, 2020, ATRIUM-11 Presubmittal Meeting ML20112F5302020-04-21021 April 2020 TVA Nuclear Plants -2019 EOC Media Loop Slides for Automatic Play (Final) ML20092F5742020-04-0202 April 2020 TVA Slides for Browns Ferry 50.69 License Amendment Request Presubmittal Meeting ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19120A3692019-04-30030 April 2019 Public Meeting Summary - Browns Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML18158A2862018-06-0707 June 2018 May 30, 2018 Summary of Public Meeting with Browns Ferry Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML17271A0162017-09-28028 September 2017 Meeting Slide for Tennessee Valley Authority (TVA) Hydrology Precipitation Model Topical Report Review Status ML17212A8432017-08-0101 August 2017 Meeting Slides for Pre-submittal Meeting with Tennessee Valley Authority on Unbalanced Voltage License Amendment Request for TVA Nuclear Plants ML17034A3322017-02-0303 February 2017 Presentation Slides for Public Meeting Regarding Browns Ferry Extended Power Uprate License Amendment Request Transmission System Update Supplements ML16341A7422017-01-0404 January 2017 Presentation Slides for Browns Ferry Pre-application Meeting Regarding Mellla+ ML16356A0342017-01-0404 January 2017 Pre-app Meeting Mellla+ LAR Final ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16189A3482016-07-19019 July 2016 Presentation Slides for July 19, 2016, Public Meeting ML16200A2592016-07-19019 July 2016 July 19, 2016: NRC Public Meeting on Browns Ferry Nuclear Plant Extended Power Uprate License Amendment Request ML16153A1982016-06-0101 June 2016 2015 EOC Meeting Summary ML16028A0962016-02-0101 February 2016 Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal Logic, and Unit Priority Re-Trip Logic License Amendment Request ML16006A2882016-01-0606 January 2016 Significant Operational Experience: 7 Major Industry Events with Regulatory Implications ML15308A1002015-11-10010 November 2015 Public Meeting Presentation Slides Extended Power Uprate License Amendment Request NRC Public Meeting ML15293A4582015-07-14014 July 2015 Slides for July 14, 2015 Public Meeting on Browns Ferry Seismic Risk Evaluations (MF3764 Through MF3766) ML15195A1252015-07-14014 July 2015 July 14, 2015 - Public Meeting Slides on Browns Ferry Seismic Risk Insights CNL-15-122, Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request2015-07-0808 July 2015 Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request ML15146A2792015-05-21021 May 2015 Bf EOC Meeting Summary 2015 ML15099A2912015-04-22022 April 2015 4/22/2015, Enclosure 2, Slides for TVA Presentation to the NRC in Support of Steam Dryer Replacement ML14147A3222014-05-27027 May 2014 Public Meeting Summary 05/21/2014 to Present Annual Assessment ML14101A1522014-04-11011 April 2014 Summary of Public and Closed Meeting for Tennessee Valley Authority 2013 Synergy Safety Culture Survey Results ML14036A3872014-02-0505 February 2014 Summary of Meeting with Public to Discuss the Results of the Follow-up Inspection of the Items Identified in Confirmatory Action Letter (ML13232A105) of August 22, 2013, and the Status of Nrc'S Performance Assessment of Browns Ferry Unit 1 ML13212A0842013-07-30030 July 2013 Summary of Public Conference Meeting with Tennessee Valley Authority to Discuss Safety Significance of One Preliminary Greater than Green Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000260/20132012 IR 05000260/20132012013-07-30030 July 2013 07/24/2013 Summary of Public Conference Meeting With Tennessee Valley Authority to Discuss Safety Significance of One Preliminary Greater Than Green Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000260 2024-02-07
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24032A2752024-02-0707 February 2024 Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21250A3012021-09-0707 September 2021 TVA Slides for September 7, 2021, Presubmittal Meeting to Discuss Planned Browns Ferry TSTF-505 License Amendment Request ML21152A1872021-06-0101 June 2021 TVA Slides for June 1, 2021, Presubmittal Meeting to Discuss Planned Control Bay Chiller Cross-Tie License Amendment Request ML24019A1322020-11-0909 November 2020 ANP-3874NP, Revision 1, Browns Ferry Atrium 11 Control Rod Drop Accident Analysis with the AURORA-B CRDA ML20175A0552020-06-23023 June 2020 TVA Slides for June 23, 2020, Emergency Plan Change Presubmittal Meeting ML20156A2812020-06-0808 June 2020 TVA Slides for June 8, 2020, ATRIUM-11 Presubmittal Meeting ML20092F5742020-04-0202 April 2020 TVA Slides for Browns Ferry 50.69 License Amendment Request Presubmittal Meeting ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML24019A1482019-01-28028 January 2019 Surveillance Procedure 2-SR-3.1.6.1, BPWS Compliance Verification, Revision 006 ML18255A0142018-09-12012 September 2018 BWROG Presentation Slides for Public Meeting Sept 12 2018 ML18255A0102018-09-12012 September 2018 NRC Slides for Target Rock Public Meeting ML18239A2522018-08-27027 August 2018 Proposed Changes to NFPA 805 License Conditions ML18158A2862018-06-0707 June 2018 May 30, 2018 Summary of Public Meeting with Browns Ferry Nuclear Plant, Docket No. 50-259, 50-260, and 50-296 ML17271A0162017-09-28028 September 2017 Meeting Slide for Tennessee Valley Authority (TVA) Hydrology Precipitation Model Topical Report Review Status ML17212A8432017-08-0101 August 2017 Meeting Slides for Pre-submittal Meeting with Tennessee Valley Authority on Unbalanced Voltage License Amendment Request for TVA Nuclear Plants ML17034A3322017-02-0303 February 2017 Presentation Slides for Public Meeting Regarding Browns Ferry Extended Power Uprate License Amendment Request Transmission System Update Supplements ML16356A0342017-01-0404 January 2017 Pre-app Meeting Mellla+ LAR Final ML16341A7422017-01-0404 January 2017 Presentation Slides for Browns Ferry Pre-application Meeting Regarding Mellla+ ML16350A2962016-12-14014 December 2016 Enclosure 3- Reactor Oversight Process Task Force FAQ Log- November 16, 2016 ML16279A2332016-10-0505 October 2016 Summary of Closed Pre-Decisional Enforcement Conference with Tennessee Valley Authority Regarding Browns Ferry Nuclear Plant ML16200A2592016-07-19019 July 2016 July 19, 2016: NRC Public Meeting on Browns Ferry Nuclear Plant Extended Power Uprate License Amendment Request ML16189A3482016-07-19019 July 2016 Presentation Slides for July 19, 2016, Public Meeting ML16028A0962016-02-0101 February 2016 Emergency Core Cooling System Preferred Pump Logic, Common Accident Signal Logic, and Unit Priority Re-Trip Logic License Amendment Request ML15308A1002015-11-10010 November 2015 Public Meeting Presentation Slides Extended Power Uprate License Amendment Request NRC Public Meeting ML15195A1252015-07-14014 July 2015 July 14, 2015 - Public Meeting Slides on Browns Ferry Seismic Risk Insights ML15293A4582015-07-14014 July 2015 Slides for July 14, 2015 Public Meeting on Browns Ferry Seismic Risk Evaluations (MF3764 Through MF3766) CNL-15-122, Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request2015-07-0808 July 2015 Presentation Slides for Closed Meeting Extended Power Uprate (EPU) License Amendment Request ML15146A2792015-05-21021 May 2015 Bf EOC Meeting Summary 2015 ML15099A2912015-04-22022 April 2015 4/22/2015, Enclosure 2, Slides for TVA Presentation to the NRC in Support of Steam Dryer Replacement ML14147A3222014-05-27027 May 2014 Public Meeting Summary 05/21/2014 to Present Annual Assessment ML14101A1522014-04-11011 April 2014 Summary of Public and Closed Meeting for Tennessee Valley Authority 2013 Synergy Safety Culture Survey Results ML14090A4582014-03-31031 March 2014 Public Meeting Summary TVA Synergy Safety Culture Survey Results ML14036A3872014-02-0505 February 2014 Summary of Meeting with Public to Discuss the Results of the Follow-up Inspection of the Items Identified in Confirmatory Action Letter (ML13232A105) of August 22, 2013, and the Status of Nrc'S Performance Assessment of Browns Ferry Unit 1 IR 05000260/20132012013-07-30030 July 2013 07/24/2013 Summary of Public Conference Meeting With Tennessee Valley Authority to Discuss Safety Significance of One Preliminary Greater Than Green Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000260 ML13212A0842013-07-30030 July 2013 Summary of Public Conference Meeting with Tennessee Valley Authority to Discuss Safety Significance of One Preliminary Greater than Green Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000260/20132012 ML13199A4522013-07-17017 July 2013 Summary of Meeting with Browns Ferry 2024-02-07
[Table view] |
Text
1m TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT (BFN)
License Amendment Request to Extend the Completion Time for an Inoperable Diesel Generator from 7 Days to 14 Days Rockville, Maryland June 29, 2010 1
lim Agenda
- Introduction Terry Cribbe
- Revised Technical Specifications (TS) Dan Green and TS Bases Changes
- BFN Electrical System Rick Sampson
- Closing Remarks Terry Cribbe 2
~ Revised TS and TS Bases Changes TS 3.8.1} AC Sources - Operating
- New Proposed Required Action B.1
- New Proposed Condition C and Required Action C.1
- Associated TS Bases Changes
3
IE] Independent Offsite Power Sources
- Robust Offsite Power Distribution System
- Seven SOOkV Lines
- Two 161kV Lines
- Six Unit Station Service Transformers (USSTs) (2 per Unit)
- Two Common Station Service Transformers (CSSTs)
- 4
,1)
Vl
"'C
~
ro 0
ce
+-'
c
..::::t:.
q 0
+-'
+-'
C QJ E
c tlO
<< ~
QJ
~
0 CO CO CO a.. rot N M l- I l-ro V") V") V")
V")
E
~
V") V")
0 z rot N M
+J
+J
. +J C C c
~
~ Alternate Power Alignment to 4kV Unit Boards
~ Normal Power Alignment to 4kV Shutdown Boards
- Unit 1- 4kV Unit Board Via 4kV Shutdown Bus 1
- Unit 2 - 4kV Unit Board Via 4kV Shutdown Bus 2
- Unit 3 - 4kV Unit Board (Direct Feed) 7
[ml Alternate Power Alignment to 4kV Shutdown Boards
- Unit 1 - 4kV Unit Board Via 4kV Shutdown Bus 2
- Unit 2 - 4kV Unit Board Via 4kV Shutdown Bus 1
- Unit 3 - 4kV Unit Board (Direct Feed) 8
~ Emergency Power Alignment to 4kV Shutdown boards
~----~----------
- The 4kV Bus Tie Board Functions as a Tie Breaker to Provide Additional Functionality (Not Credited in Accident Analysis)
lim 4kV System Supplies Entire Plant
- Safety-Related Loads - USSTs 1B, 2B and 3B
- Non-Safety (Balance of Plant) Loads - USSTs lA, 2A and 3A 10
[ml 4kV Standby Power (If Offsite Power is Lost)
- Unit 1 and Unit 2 Share 4 Diesel Generators (DGs)
- Unit 3 DGs Can Be Aligned (Direct Cross-Tie) to Supply Unit 1/2 4kV Shutdown Boards (Does Not Require the 4kV Bus Tie Board)
- Unit 1/2 DGs Can Be Aligned (Direct Cross-Tie) to Supply Unit 3 4kV Shutdown Boards (Does Not Require the 4kV Bus Tie Board) 11
um Example Unit 1 Alignment - DG A Out of Service
- Utilize DG 3EA as Alternate Supply for 4kV Shutdown Board A via the Tie Breakers on 4kV Shutdown Board A and 3EA
- Utilize DG 3EA as Emergency Supply to 4kV Shutdown Board A via the 4kV Bus Tie Board (Only If Options 1 or 2 Were Not Available - This Option Is Not Qualified) 12
[rnl Example Unit 2 Alignment - DG C Out of Service
- Utilize DG 3EC as Alternate Supply for 4kV Shutdown Board C via the Tie Breakers on 4kV Shutdown Board C and 3EC
- Utilize DG 3EC as Emergency Supply to 4kV Shutdown Board C via the 4kV Bus Tie Board (Only If Options 1 or 2 Were Not Available - This Option Is Not Qualified) 13
1m Example Unit 3 Alignment - DG 3EA Out of Service
- Utilize DG A as Alternate Supply for 4kV Shutdown Board 3EA via the Tie Breakers on 4kV Shutdown Board 3EA and A
- Utilize DG 3EB as Emergency Supply for 4kV Shutdown Board 3EA via the 4kV Bus Tie Board (Only If Options 1 or 2 Were Not Available - This Option Is Not Qualified) 14
Iii DG Loading
- Load Shedding Performed As Necessary to Utilize Alternate Feeds/Alignments
- Loading Monitored In Accordance With Operating Instructions
- Load Restrictions, Where Necessary, On Single Line Drawings As Operating Limit (OPL) Notes
- OPL Notes Referenced in Operating Instructions is
E OJ
+J V)
~
ro u
.L..
+J U
('\..
-UJOJ V) c Z o
- u. 0
~
co V)
OJ
~
o
Ii!i! PRA Supporting DG 14 Day Completion Time
,~----------
- BFN PRA Upgrade
- Risk Insights from DG Completion Time Studies 17
Ii!i] Introd uction
_ _ _.m *
- Unit 1 BFN PRA RISKMAN Model Updated in 2006
- Significant Findings and Observations (F&Os) Found During Peer Review
- RISKMAN Software Requires More Resources to Understand, Develop and Apply
- PRA Upgrade Began in 2007
- Model Converted from RISKMAN to CAFTA
- Every Element of Model Re-Examined
- Peer Review of Internal Events May 2009
- Peer Review of Internal Flooding August 2009 18
lim
_~_,_~~~,,~~,
Programs/Tools Used for Conversion
Software Package Version Description CAFTA 5.4 Computer Aided Fault Tree Analysis System PRAQuant 5.0a PRAQuant Accident Sequence Quantification FTREX 1.4 Fault Tree Reliability Evaluation eXpert HRA Calculator 4.0 Human Reliability Analysis Calculator MAAP 4.0.5 Modular Accident Analysis Program 19
U!4! General Aspects of Upgrade
- New CAFTA Model Integrates All Three Units
- Allows Evaluation of Risk for All Units for Outage of Common Systems, Structures, and Components
- Allows Simultaneous Update for Data
- New Calculations Issued for All PRA Elements
- PRA Updates Follow Industry PRA Configuration and Control Practices 20
um Initiating Events (IE)
- 101 New Initiators Added to 3-Unit Model
- 57 Flood Initiators Replaced 7 Previously Modeled
- 3 Initiators Added for Intake Structure Plugging (1 per Unit)
- 51 Initiators Added for Various Combinations of AC and DC Electrical Board Failures
- Initiators That Could Affect More than 1 Unit Considered
- Previous Peer Review Findings Resolved
- Bayesian Update of Industry IE with Plant Specific Data 21
[i!i! Accident Sequences
- IEs Grouped and Evaluated Collectively
- Event Trees Developed for Each Accident Class (e.g.} Large LOCA} General Transient} etc.)
- Operations Personnel Interviewed to Reflect Plant Responses 22
1m Success Criteria
- All Success Criteria Re-Evaluated for PRA Upgrade
- Realistic Success Criteria Established
- Existing Safety Analyses Reviewed for Applicability
- Plant Specific Thermal Hydraulic (T-H) Calculations Performed
- T-H analyses Based on MAAP 4.0.5 runs 23
1m Systems Analysis
- All Systems in PRA Re-Evaluated
- Includes All Systems that are
- Required for Accident Mitigation
- Systems Supporting Accident Mitigating Systems
- Ensured Models are Consistent With As-Built As-Operated Plant
- System Engineers Reviewed Documentation 24
1m Data Analysis
- Freeze Date for Data was January 2008
- Bayesian Updated with Plant Specific Data
- Unavailability Data Based on
- Maintenance Rule Data
- System Engineer/Operations Staff Estimates
- Data Will Be Updated Every 4 Years
- Common Cause Failures Accounted for Within Systems 25
[m! Human Reliability Analysis (HRA)
- Document and Quantify all Independent Human Error Probabilities
- Document and Quantify Human Error Probabilities for Dependent Actions
1m Internal Flooding
- Several Walkdowns Performed to Assess the Impact of Flooding, Spray, and Impingement
- Peer Reviewed in August 2009
Ii!4! Large Early Release Frequency (LERF) Analysis
- New Containment Event Trees Developed
- New MAAP Analyses Performed to Define Realistic LERF Sequences 28
1m Quantification
- Single Fault Tree (for each Unit) Quantified Using CAFTA and FTREX 1.4
- Uncertainty Analysis Performed Quantitatively Using UNCERT
- Sensitivity Studies Performed for Significant Modeling Uncertainties 29
1m Modeling for DG Completion Time
- Additional Initiators Added to Evaluate Fires That Could Cause Loss of Offsite Power
- Impact of Extended DG Completion Time On All Units Evaluated for each DG 30
Summary Of Risk Impact of EDG lim (I nternal Events)
Table 4. Effect on CDF and LERF of 14-Day DG AOT Unavailability DG Using Base PRA Unavailability Case Model 14-Day AOT Change 0/0 Change U1 CDF 6.57E-06 6.67E-06 9.49E-08 1.44%
U2CDF G.B8E-06 6.95E-06 7.74E-08 1.130/0 U3CDF 7.30E-06 7.53E-06 2.29E-07 3.13%
U1 LERF 2.13E-06 2.14E-06 6.80E-09 0.320/0 U2 LERF 2.70E-06 2.71 E-06 4.90E-09 0.180/0 U3 LERF 1.01E-06 1.02E-06 5.10E-09 0.500k 31
Summary Of Risk Impact of EDG
[lID (Fire-Induced LOOP Events)
Table 5. FIVE Scenarios with Plant Response Bounded bv Loss of Offsite Power Severe Fire Area / Fire Description Fire Major Fire New Initiator Zone FreQuencv Factor FreQuency Name*
16-3 (case 2B) Control Building - 617' 4.62E-05 0.049 2.26E-06 %xlOOPFRCB (Control Room) 24 4kV Bus Tie Board Room 1.92E-02 0.10 1.92E-03 %xLOOPFRBT 25-3 (case 38) Turbine Deck 1.34E-02 0.119 1.59E-03 %xlOOPFRTD Yard Area Yard Area 5.10E-03 0.25 1.28E-03 %xLOOPFRYD (case 2)
- There are four new fire initiators per unit (x in the Init Name = unit number) 32
Summary Of Risk Impact of EDG lim (Fire-Induced LOOP Events)
Table 6. Effect on CDF and LERF of 14-Day DG AOT Unavailability for Fires Resulting in a LOOP DG Using Base PRA Unavailability Case Model 14-Day AOT Change °/0 Change U1 CDF 1.22E-06 1.35E-OS 1.28E-07 10.44°/0 U2CDF 9.92E-07 1.08E-06 8.97E-08 9.05°10 U3CDF 2.26E-OS 2.53E-06 2.74E-07 12.14°t'o U1 LERF 2.25E-07 2.33E-07 7.95E-09 3.54°t'o U2 LERF 2.03E-07 2.08E-07 4.49E-09 2.21%
U3 LERF 1.83E-07 1.8SE-07 3.38E-09 1.85%
33
Summary Of Risk Impact of EDG
[m (Total Including Internal and Fire)
Table 7. Total Effect on CDF and LERF of 14-Day DG AOT Unavailability DG Using Base PRA Unavailability Case Model 14-Day AOT Change % Change U1 CDF 7.79E-06 8.01E-06 2.23E-07 2.86%
U2CDF 7.87E-06 8.03E-06 1.67E-07 2.12%
U3CDF 9.56E-06 1.01E-05 5.02E-07 5.26%
U1 LERF 2.36E-06 2.37E-06 1.48E-08 0.63%
U2 LERF 2.90E-06 2.91E-06 9.39E-09 0.32%
U3 LERF 1.19E-06 1.20E-06 8.48E-09 0.71%
34
1m PRA Conclusions
- BFN PRA Model Significantly Upgraded Since 2006
c Q)
E Vl Vl Q)
Vl Vl
~
.-Vl a::
.......,u V')
('0
..c Vl c
co 0
..c ......,
0 Vl s... Q) a.. :J cJ I
~
V')
~
~
CO E
Q) a::
tlO c
V')
-uo fl:Il