Letter Sequence Meeting |
|---|
|
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance...
- Supplement, Supplement, Supplement, Supplement, Supplement, Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting, Meeting
Results
Other: ML070370281, ML073100027, ML073510180, ML080360067, ML080430700, ML080500171, ML080530256, ML081010450, ML081010451, ML081120502, ML081700294, ML081720078, ML081760295, ML082040065, ML082050462, ML082100425, ML082810470, ML083120308, ML083240224, ML083250083, ML090130718, ML090340528, ML090720951, ML090760630, ML091320366, ML092020345, ML092430520, ML092440518, ML092460495, ML092460496, ML092460497, ML092460498, ML092460500, ML092540483, ML092680057, ML12319A076, ML13044A498
|
MONTHYEARML0631104352006-11-0707 November 2006 Report of Emergency Core Cooling System (ECCS) Evaluation Model Changes Project stage: Request 05000260/LER-2007-001, Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test2007-03-0202 March 2007 Re Automatic Turbine Trip and Reactor Scram Due to Equipment Failure During Performance of the Main Generator Rheostat Test Project stage: Request ML0711300782007-04-18018 April 2007 Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Supplemental Response to Requests for Additional Information (RAI) Project stage: Supplement ML0711503662007-04-24024 April 2007 Units 1, 2, & 3 - Fire Protection Program - Post-Fire Operator Manual Actions Project stage: Request ML0711503712007-04-24024 April 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Evaluations Project stage: Request ML0712905652007-05-16016 May 2007 Withholding Information from Public Disclosure, Response to Nuclear Regulatory Commission (NRC) Request for Additional Information - Round 12 for Browns Ferry EPU: Supplemental to SBWB-64 Project stage: RAI ML0716303492007-06-15015 June 2007 Meeting with the Tennessee Valley Authority Concerning the Status of Browns Ferry Nuclear Plant, Units 1, 2 and 3, Steam Dryer Review Project stage: Meeting ML0718700242007-07-0303 July 2007 Technical Specifications (TS) Change TS-461 - Modification of Restart Large Transient Testing License Condition 2. (G) 2 - Supplement 1 Project stage: Request ML0717801902007-07-0505 July 2007 Request for Additional Information for Extended Power Uprate - Round 13 (TS-431 and TS-418 Project stage: RAI ML0719004762007-07-10010 July 2007 Meeting with the Tennessee Valley Authority (TVA) Concerning the Pending ACRS Meeting on the Browns Ferry Extended Power Uprate Project stage: Meeting ML0721501562007-07-18018 July 2007 Slides from Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting ML0721303712007-07-27027 July 2007 Technical Specifications Changes TS-431 and TS-418, Extended Power Uprate - Steam Dryer Evaluations Project stage: Request ML0721303752007-07-31031 July 2007 CDI Report No. 07-05NP, Revision 0, Finite Element Model for Stress Assessment of Browns Ferry, Unit 1, Steam Dryer to 250 Hz Project stage: Request ML0721400442007-08-0808 August 2007 Summary of Meeting with Tennessee Valley Authority on the Browns Ferry Power Uprate ACRS Presentation Project stage: Meeting 05000259/LER-2007-005, Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank2007-08-0808 August 2007 Regarding Automatic Reactor Scram Due to Turbine Trip as a Result of Invalid High Level in Moisture Separator Drain Tank Project stage: Request ML0723602572007-08-21021 August 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Steam Dryer Limit Curves Project stage: Request ML0724805472007-08-31031 August 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure Project stage: Request ML0727606602007-10-0909 October 2007 Request for Additional Information for Extended Power Uprate - Round 14 (TS-418) Project stage: RAI ML0728902372007-10-18018 October 2007 Request for Withholding Information from Public Disclosure Concerning Round 13 Request for Additional Information for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263 and MD5264) Project stage: RAI ML0729603112007-10-22022 October 2007 Technical Specification (TS) Changes TS-431 & TS-418, Extended Power Uprate - EPU Large Transient Testing Project stage: Request ML0731000272007-11-0909 November 2007 Request for Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418-S) Project stage: Other ML0732303482007-11-15015 November 2007 Units 1, 2, and 3 - Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 13 Request for Additional Information (RAI) - Containment Overpressure APLA-35/37 Project stage: Request ML0733304832007-11-21021 November 2007 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Preliminary Findings on Steam Dryer Stress Analysis Project stage: Request 05000296/LER-2007-003, Leak in an ASME Class I Code Reactor Pressure Boundary Pipe2007-11-21021 November 2007 Leak in an ASME Class I Code Reactor Pressure Boundary Pipe Project stage: Request ML0735101802007-12-14014 December 2007 Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Schedule Regarding Analysis for Steam Dryers Project stage: Other ML0734607572007-12-19019 December 2007 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac No. MD5262, MD5263 and MD5264) Project stage: Withholding Request Acceptance ML0735400102008-01-25025 January 2008 Summary of Meeting with Tennessee Valley Authority on Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264), Browns Ferry Units 1, 2, and 3 Project stage: Meeting ML0801504182008-01-25025 January 2008 (Public Version) - Summary of December 10, 2007 Meeting with TVA on Steam Dryer Portion of the Extended Power Uprate Review Project stage: Meeting ML0803205212008-01-25025 January 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) Response to Round 15 Request for Additional Information (RAI) - APLA-38/40, SRXB-71, and SRXB-72 Project stage: Request ML0803600672008-01-25025 January 2008 Steam Dryer RAI 15 Status, Slides Project stage: Other ML0802501652008-01-30030 January 2008 Request for Withholding Information from Public Disclosure for Browns Ferry Nuclear Plant (Tac Nos. MD5262, MD5263, and MD5264) Project stage: Withholding Request Acceptance ML0803805602008-01-31031 January 2008 Technical Specifications (TS) Change TS-431 and TS-418 - Extended Power Uprate (EPU) - Response to Round 15 Request for Additional Information (RAI) Regarding Steam Dryer Analyses Project stage: Request ML0804307002008-02-11011 February 2008 Technical Specifications (TS) Changes TS-431 and TS-418 - Extended Power Uprate (EPU) - Schedule Regarding EPU Project stage: Other ML0804304462008-02-11011 February 2008 Notification of Potential Part 21 Report Power Supply Unit Is Limited at Elevated Temperatures Project stage: Request ML0803503812008-02-14014 February 2008 Summary of Meeting with Tennessee Valley Authority - on Extended Power Uprate Review Project stage: Meeting ML0806501012008-02-21021 February 2008 Response to Round 16 Request for Additional Information SRXB-73 Project stage: Request ML0805302562008-02-21021 February 2008 Unit 1 - Technical Specifications (TS) Change TS-431 - Extended Power Uprate (EPU) - Fuels Methods Commitments Project stage: Other ML0804506472008-02-27027 February 2008 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML0803506982008-02-29029 February 2008 Request for Additional Information for Extended Power Uprate - Round 16 (TS-431 and TS-418) (TACs MD5262, MD5263, MD5264) Project stage: RAI ML0807104982008-03-0606 March 2008 (BFN) - Units 1, 2, and 3 - Technical Specifications (TS) Change TS-418 and TS-431 - Extended Power Uprate (EPU) - Response to Round 16 Request for Additional Information (RAI) - SRXB-74/86 and SRXB-87 Through SRXB-90 Project stage: Request ML0811205102008-03-20020 March 2008 Summary of March 20, 2008, Meeting with Tennessee Valley Authority Regarding Steam Dryer Portion of the Extended Power Uprate Review (TAC Nos. MD5262, MD5263, and MD5264) - Slides Project stage: Meeting ML0810104502008-04-0404 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 Project stage: Other ML0810104512008-04-0404 April 2008 Technical Specifications (TS) Changes TS-431 and TS-418 Extended Power Uprate (EPU) BFN Steam Monitoring Plan Project stage: Other ML0817602952008-04-0909 April 2008 Units 1, 2, & 3 - Technical Specifications Changes TS-431 and TS-418 - Extended Power Uprate - Confirmation of Commitment Completions Project stage: Other ML0811205022008-04-16016 April 2008 CDI Incoming Letter Dated April 16, 2008 Regarding NRC Presentation Entitled, Tennessee Valley Authority Browns Ferry Nuclear Plant - Extended Power Uprate Steam Dryers Project stage: Other ML0811302312008-04-17017 April 2008 Public Slides - Summary of April 17, 2008, Meeting Regarding Steam Dryer Portion of the Extended Power Uprate Review, Project stage: Meeting ML0811200332008-04-30030 April 2008 Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Browns Ferry Nuclear Plant, Units 1, 2, and 3 - Request for Withholding Information from Public Disclosure for Round 15 Fuels Responses Project stage: Withholding Request Acceptance ML0812806272008-05-0101 May 2008 Technical Specifications Change TS-418, Extended Power Uprate Supplemental Response to Round 16 Request for Additional Information - SRXB-87 & SRXB-89 Project stage: Supplement ML0812804712008-05-0202 May 2008 Request for Additional Information for Extended Power Uprate - Round 17 Project stage: RAI ML0805001712008-05-0202 May 2008 Schedule Regarding Analysis for Steam Dryers on Extended Power Uprate Amendment Requests (TAC Nos. MD5262, MD5263, and MD5264) (TS-431 and TS-418) Project stage: Other 2007-07-05
[Table View] |
Text
Imi TENNESSEE VALLEY AUTHORITY BROWNS FERRY NUCLEAR PLANT POWER UPRATE ACRS CONTAINMENT OVERPRESSURE (COP)
Rockville, Maryland July 10, 2008
Introduction
" COP Part of BFN Current Licensing Basis for Appendix R and LOCA
- EPU Results in Additional COP need in Licensing Basis Analysis
- ACRS Concerns from Unit 1 105% Review Magnitude and duration of Appendix R event Feasibility of protecting second RHR pump Consider external initiators when using risk-informed arguments for the Appendix R COP credit Realistic long-term LOCA analysis needs to be supported by more defensible sensitivity analyses James Emens 2
Introduction Actions Taken to Address ACRS Concerns on Appendix R COP July 2007 meeting with NRC Staff Fire area analysis undertaken to compare COP needs for, realistic fire versus Appendix R analysis Deterministic analysis to provide risk insight o Submitted November 15, 2007 Followed-up with NPSH analysis for limiting cases o Submitted June 12, 2008 James Emens 3
Alternate Fire Shutdown Analysis Appendix R Rule Based Fire
- Prescribed Appendix R fire damage o Loss of all equipment not meeting generic separation criteria o Fire damage not based on analysis Fire damage overly conservative for many areas of the plant J. D. Wolcott 4
Alternate Fire Shutdown Analysis Fire Hazards Analysis
- Supplement to Appendix R Fire damage by analysis versus prescribed fire damage Screen based on fire protection parameters o Combustible loading o Volume of fire area o Detection/Suppression o Ignition sources 22/39 fire areas screened out o Fire limited to ignition source o No wide spread fire damage 17 fire areas screen in o Evaluated for equipment availability J. D. Wolcott 5
Alternate Fire Shutdown Analysis Equipment Availability Analysis All equipment in fire area assumed lost in 17 fire areas Unaffected equipment used per EOIs Offsite power credited where unaffected o BOP systems available in many areas 15/17 areas do not need COP o Sufficient equipment available to limit pool temperature Only 2 fire areas need some COP o Electrical Board Rooms J. D. Wolcott 6
Alternate Fire Shutdown Analysis e NPSH Analysis - Limiting Fire Areas Minimum equipment o Emergency depressurization o Reactor water level maintained with BOP o One RHR pump for containment cooling Pool water volume increased during event o Peak pool temperature lower o Pool level/elevation head increase Relaxed NPSHr based on revised vendor report o Based on shorter operating time consideration Termination of drywell coolers not required J. D. Wolcott 7
Alternate Fire Shutdown Analysis NPSH RESULTS
- Significant reduction in COP required o01/2 psi COP o 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> duration
- Significant COP margin o Minimum 8 psi Core cooling not dependent on COP o Core cooling by BOP Systems o Defense-In-Depth consideration J. D. Wolcott 8
COP Available and COP Required Alternate Fire Hazards Analysis 30 220 Suppression Pool Temnerature 200 I
180 160 Cotanment 25 2
20 J 140 120 100 Atmospheric Pressure 15 RHR Pump Containment Pressure Required 10 0
10 20 30 40 50 Time, Hours 60 J. D. Wolcott 9
COP Available and COP Required IM Licensing Basis Appendix R 30 220 -
SuppressionPo J
Temperatr 200-25 180 16 0______
P umpC ontainm ent 20 10Containment Pressure Pesr Required 140-15 Atmospheric Pressure 120 100 10 0
10 20 30 40 50 60 Time (hours)
J. D. Wolcott 10
Specific ACRS Recommendations IM Feasibility of Second RHR Pump for Appendix R Extensive resources o Physical location of switchgear o Shared electrical system o Support equipment 13 Valves/controls 0 Diesel generator/controls o RHRSW pump/valves o Significant modifications o Significant program and licensing changes Minimal safety benefit o Demonstrated by fire hazards analysis J. D. Wolcott 11
Specific ACRS Recommendations IIVAI "I
, Consideration of External Events in Fire Risk Evaluations Fire risk insights from deterministic fire hazards analysis o Not a PRA analysis
.o Bounding fire is assumed J. D. Wolcott 12
Appendix R Conclusions
" Licensing Basis Analysis Complies With Appendix R and Demonstrates a Success Path
" COP Magnitude and Duration for Appendix R Driven by Rule Based Assumptions
" Fire Hazards Analysis Shows Reduced or No Dependency on COP J. D. Wolcott 13
Additional ACRS Issue 11VA1
- Bias and Uncertainty in Realistic LOCA Realistic LOCA used to build PRA model for COP Use of 95% non-exceedance values Use of probability distributions Use of conservative licensing basis methods Realistic NPSH analyses biased conservatively J. D. Wolcott 14
Closing
- Concluding Remarks James Emens 15