|
|
| (8 intermediate revisions by the same user not shown) |
| Line 2: |
Line 2: |
| | number = ML15236A134 | | | number = ML15236A134 |
| | issue date = 08/26/2015 | | | issue date = 08/26/2015 |
| | title = Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (TAC Nos. MC4702, MC4703, and MC4704) | | | title = Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 |
| | author name = Watford M M | | | author name = Watford M |
| | author affiliation = NRC/NRR/DORL/LPLIV-1 | | | author affiliation = NRC/NRR/DORL/LPLIV-1 |
| | addressee name = Edington R K | | | addressee name = Edington R |
| | addressee affiliation = Arizona Public Service Co | | | addressee affiliation = Arizona Public Service Co |
| | docket = 05000528, 05000529, 05000530 | | | docket = 05000528, 05000529, 05000530 |
| | license number = NPF-041, NPF-051, NPF-074 | | | license number = NPF-041, NPF-051, NPF-074 |
| | contact person = Watford M M | | | contact person = Watford M |
| | case reference number = TAC MC4702, TAC MC4703, TAC4704 | | | case reference number = TAC MC4702, TAC MC4703, TAC4704 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
| | page count = 11 | | | page count = 11 |
| | project = TAC:MC4702, TAC:MC4703 | | | project = TAC:MC4702, TAC:MC4703 |
| | stage = | | | stage = Meeting |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:Palo Verde Nuclear Generating StationGeneric Letter 2004-02August 26th, 2015 IntroductionsTom WeberDepartment LeaderNuclear Regulatory Affairs | | {{#Wiki_filter:Palo Verde Nuclear Generating Station Generic Letter 2004-02 August 26th, 2015 |
|
| |
|
| ==Background== | | ===Introductions=== |
| *12/18/2013 -APS submitted Revision 2 to Supplemental Response to NRC Generic Letter 2004-02*4/15/2015 -PVAR 4644513 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel*6/10/2015 -Initial Public Meeting with NRC-Beaver Valley Operating Experience with Microtherm-Communication with the Industry-Industry Testing of Microporous Insulation-Extent of Condition3 Microtherm Locations4 Break LocationsLimiting Break Location Steam Generator Hot Leg NozzleReactor Pressure Vessel (RPV) Nozzle break locations5 Extent of ConditionRed: Temp-Mat Impacting Existing Break Location(SG HL Nozzle)6Green: Temp-Mat Impacting New RPV Break LocationLOCATIONUnit 1Unit 2Unit 3Cold Leg 1A, 1B, 2A, 2B RTDXXXBelow RPV NozzleXXXRPV CavityXXXRPV ICIsXXXCrossover 1A, 1B, 2A, 2B RCP NozzleXCrossover 1A, 1B, 2A, 2B SG NozzleXCold Leg 1A, 1B, 2A, 2B RPV ElbowXUnit 3 Only Analysis to date*Debris Generation-Primary success path is removal of Temp-Mat in the D-rings for current limiting break-Microtherm ZOI (zone of influence) based on robustness of encapsulation-Encapsulated Microtherm ZOI and restrained separation of pipe at RPV nozzle break limits Microtherm quantity to the local region of the break location*Debris Transport-RPV nozzle break -Temp-Mat generated to the Reactor Cavity will not transport to strainers based on very low flow velocity and upward vertical flow path of 18 to 23 feet*Cold Leg RPV Elbow Temp-Mat is still being analyzed for impact (Unit 3 Only)-Generated Microtherm assumed to transport to the strainers7 Analysis to date (cont)*Industry Testing / NPSH-Salem U2 Test 6 Head Loss conditions (with Min-K) bound Palo Verde with Microtherm for post-LOCA flow scenarios-Comparative analysis indicates Palo Verde NPSH and structural limits should be bounded by existing SG HL Break location8 Actions to finalize*Confirm Removal of Temp-Mat from D-ring*Confirm Removal of Temp-Mat from Unit 3 RPV Cold Leg Elbows*Confirm impact of identified Temp-Mat and Microtherm for RPV on chemical effects*Finalize LPSI pump failure to trip after Recirculation Actuation Signal (RAS) | | Tom Weber Department Leader Nuclear Regulatory Affairs |
| Scenario*Complete final review of assessment report9 Summary*A resolution path exists for D-ring and RPV nozzle break cases-Confirmation of chemical effects and LPSI flow scenario items in process-Open Strainer Area is expected to be comparable with original analysis*Confirm removal of Temp-Mat in D-Ring-Removal of RTD Temp-Mat (all 3 units)-Removal of Crossover Piping Temp-Mat in Unit 3*Confirm removal of Cold Leg RPV Elbows in Unit 3 *Supplement APS Response to GL 2004-0210 11We SAFELYand efficientlygenerate electricity for the long term | | |
| }} | | ===Background=== |
| | * 12/18/2013 - APS submitted Revision 2 to Supplemental Response to NRC Generic Letter 2004-02 |
| | * 4/15/2015 - PVAR 4644513 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel |
| | * 6/10/2015 - Initial Public Meeting with NRC |
| | - Beaver Valley Operating Experience with Microtherm |
| | - Communication with the Industry |
| | - Industry Testing of Microporous Insulation |
| | - Extent of Condition 3 |
| | |
| | Microtherm Locations 4 |
| | |
| | Break Locations Reactor Pressure Vessel (RPV) Nozzle break locations Limiting Break Location Steam Generator Hot Leg Nozzle 5 |
| | |
| | Extent of LOCATION Unit 1 Unit 2 Unit 3 Cold Leg 1A, 1B, 2A, 2B RTD X X X Below RPV Nozzle X X X Condition RPV Cavity RPV ICIs Crossover 1A, 1B, 2A, 2B RCP X |
| | X X |
| | X X |
| | X Nozzle X Crossover 1A, 1B, 2A, 2B SG Nozzle X Cold Leg 1A, 1B, 2A, 2B RPV Elbow X Red: Temp-Mat Impacting Existing Break Location (SG HL Nozzle) |
| | Green: Temp-Mat Impacting New RPV Break Location Unit 3 Only 6 |
| | |
| | Analysis to date |
| | * Debris Generation |
| | - Primary success path is removal of Temp-Mat in the D-rings for current limiting break |
| | - Microtherm ZOI (zone of influence) based on robustness of encapsulation |
| | - Encapsulated Microtherm ZOI and restrained separation of pipe at RPV nozzle break limits Microtherm quantity to the local region of the break location |
| | * Debris Transport |
| | - RPV nozzle break - Temp-Mat generated to the Reactor Cavity will not transport to strainers based on very low flow velocity and upward vertical flow path of 18 to 23 feet |
| | * Cold Leg RPV Elbow Temp-Mat is still being analyzed for impact (Unit 3 Only) |
| | - Generated Microtherm assumed to transport to the strainers 7 |
| | |
| | Analysis to date (cont) |
| | * Industry Testing / NPSH |
| | - Salem U2 Test 6 Head Loss conditions (with Min-K) bound Palo Verde with Microtherm for post-LOCA flow scenarios |
| | - Comparative analysis indicates Palo Verde NPSH and structural limits should be bounded by existing SG HL Break location 8 |
| | |
| | Actions to finalize |
| | * Confirm Removal of Temp-Mat from D-ring |
| | * Confirm Removal of Temp-Mat from Unit 3 RPV Cold Leg Elbows |
| | * Confirm impact of identified Temp-Mat and Microtherm for RPV on chemical effects |
| | * Finalize LPSI pump failure to trip after Recirculation Actuation Signal (RAS) |
| | Scenario |
| | * Complete final review of assessment report 9 |
| | |
| | Summary |
| | * A resolution path exists for D-ring and RPV nozzle break cases |
| | - Confirmation of chemical effects and LPSI flow scenario items in process |
| | - Open Strainer Area is expected to be comparable with original analysis |
| | * Confirm removal of Temp-Mat in D-Ring |
| | - Removal of RTD Temp-Mat (all 3 units) |
| | - Removal of Crossover Piping Temp-Mat in Unit 3 |
| | * Confirm removal of Cold Leg RPV Elbows in Unit 3 |
| | * Supplement APS Response to GL 2004-02 10 |
| | |
| | We SAFELY and efficiently generate electricity for the long term 11}} |
Letter Sequence Meeting |
|---|
|
|
MONTHYEARML0515202672005-06-0202 June 2005
6/2/05, Palo Verde, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
Project stage: RAI
ML0603903502006-02-0909 February 2006
RAI, Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-basis Accidents at Pressurized-Water Reactors (TAC Nos. MC4702, MC4703, and M4704)
Project stage: RAI
ML0833701622008-11-14014 November 2008
Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2, and 3, Notification and Concurrence of Extension for Submittal of the Revised Supplemental Response to NRC Generic Letter 2004-02
Project stage: Request
ML0832503462008-11-14014 November 2008
E-Mail Response Re Licensee'S Request for Extension to Revised Supplemental Response to Generic Letter 2004-02
Project stage: Other
ML0832309372008-12-0303 December 2008
Extension Request for Submittal of the Revised Supplemental Response to Generic Letter 2004-02
Project stage: Other
ML0834305492008-12-16016 December 2008
Request for Additional Information Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors
Project stage: RAI
ML15156B3522015-06-0404 June 2015
Draft Slides for Public Meeting with Arizona Public Service Company Ongoing Resolution of Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15236A1342015-08-26026 August 2015
Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
Project stage: Meeting
ML15239B3222015-09-0909 September 2015
Summary of Public Meeting Via Conference Call with Arizona Public Service Company Regarding Ongoing Resolution of Generic Letter 2004-02 for Palo Verde, Units 1, 2, and 3
Project stage: Meeting
ML15268A1312015-10-0505 October 2015
Summary of Public Meeting Via Conference Call with Arizona Public Service Company Regarding Ongoing Resolution of Generic Letter 2004-02 for Palo Verde, Units 1, 2, and 3
Project stage: Meeting
ML15348A0542015-12-15015 December 2015
Slides for December 17, 2015 Public Meeting with APS on Resolution of GL 2004-02
Project stage: Meeting
2008-12-03
[Table View] |
|
|---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24038A1742024-02-0707 February 2024
Pre-submittal Meeting 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
ML24003A8532024-01-0303 January 2024
January 4, 2024 Presubmittal Meeting Presentation-Risk Informed Process for Evaluations (RIPE) License Amendment Request for Safety Injection Tank (SIT) LCO (EPID: L?2023?LRM-0108)
ML23240A3232023-08-31031 August 2023
APS Presentation Slides for Pre-Submittal Meeting on 8/31/23, Alloy-600 Management Program Plan
ML23192A0102023-07-11011 July 2023
NRC RIPE 7-11-23 Public Meeting Presentation Slides
ML23144A0252023-05-25025 May 2023
APS Presentation Slides for Pre-Submittal Meeting on 5/25/23, Przr Surge Line
ML23093A0252023-04-30030 April 2023
April 5, 2023, Presubmittal Meeting Presentation - Containment Temperature and Safety Injection Tank Volume Requirements LAR
ML23090A1392023-04-0404 April 2023
April 4, 2023 Presubmittal Meeting Presentation - LAR to Adopt TSTF-266, Eliminate the Remote Shutdown System Table of Instrumentation and Controls (EPID: L?2023?LRM-0017)
ML23055B0572023-03-0101 March 2023
March 1, 2023 Presubmittal Meeting Presentation - Request for Use of Mururoa V4F1 and MTH2 Supplied Air Suits (EPID: L?2023?LRM-0012)
ML22096A0052022-04-0606 April 2022
TSTF-487 LAR Pre-submittal Public Meeting Presentation Slides
ML22025A0012022-01-25025 January 2022
1/25/22 Pre-submittal Meeting Presentation Slides for RR-69 to Extend Containment Tendon Inspection by Three Months Beyond 2/8/22
ML21342A0502021-12-0808 December 2021
TSTF-567 LAR Pre-submittal Public Meeting Presentation Slides
ML21320A1032021-11-17017 November 2021
RIPE Exemption 11-17-21 Pre-submittal Public Meeting Presentation Slides
ML21194A2502021-08-10010 August 2021
RIC 2021 - Ai EPRI-Artificial Intelligence and Development at EPRI
ML21131A0132021-05-13013 May 2021
License Transfer from Pnm to SRP, 5-13-21 Pre-submittal Public Meeting Presentation Slides
ML21025A0032021-01-26026 January 2021
Risk-Informed Process for Evaluations (RIPE) - NEI Public Meeting Presentation Slides
ML21025A0042021-01-25025 January 2021
Risk-Informed Process for Evaluations (RIPE) - NRC Public Meeting Presentation Slides
ML20171A2352020-06-24024 June 2020
Inservice Testing - Supplemental Position Indication Relief Request - NRC Pre-Application Meeting - June 24, 2020
ML19192A0972019-07-11011 July 2019
License Amendment Request for Emergency Plan, July 11, 2019
ML18299A0722018-09-26026 September 2018
Ionizing Radiation Factsheet-Veterans - Information for Veterans and Their Families
ML17320A1932017-11-15015 November 2017
NRC Public Meeting, Treatment of Mitigating Strategies in Risk Informed Decision Making
ML17003A0332016-12-29029 December 2016
Enclosure 2 - APS Meeting Slides
ML16357A6872016-12-20020 December 2016
One-Time License Amendment Request Unit 3 Train B Diesel Generator
ML17003A0862016-11-0303 November 2016
Enclosure 2 Slides Regulatory Audit Report for November 2-3, 2016
ML16253A4112016-09-0707 September 2016
Palo Verde Nuclear Generating Station Generic Letter 2004-02 - September 7, 2016
ML16083A4722016-03-24024 March 2016
NRC Subsequent Pre-Submittal Meeting Next Generation Fuel - Palo Verde, Units 1, 2, and 3
ML16014A1102016-01-20020 January 2016
Draft APS Slides for January 20, 2015, Public Meeting with APS Regarding Upcoming Next Generation Fuel License Amendment Request for Palo Verde, Units 1, 2, and 3
ML15244B2632015-08-27027 August 2015
Slides for Public Meeting with Arizona Public Service Company to Discuss License Amendment Request for Palo Verde Regarding Revised Methodology for Spent Fuel Pool Criticality Analysis
ML15236A1342015-08-26026 August 2015
Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15159B2972015-06-0909 June 2015
Near-Term Task Force Recommendation 2.1 (R2.1) Seismic Hazard Evaluation - Arizona Public Service, Palo Verde Nuclear Generating Station Public Meeting - June 9, 2015
ML15156B3312015-06-0909 June 2015
Public Meeting Slides on R2.1 Seismic Hazard Re-Evaluation
ML15156B3522015-06-0404 June 2015
Draft Slides for Public Meeting with Arizona Public Service Company Ongoing Resolution of Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15134A3592015-05-11011 May 2015
5/11/2015, Meeting Slide Regarding Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality Analysis
ML15126A2072015-05-11011 May 2015
Presentation Slides for Prelicensing Meeting with Arizon Public Service Company to Discuss License Amendment Request for Palo Verde, Units 1, 2, and 3,
ML15103A2882015-04-0909 April 2015
Presentation on Potential Relief Request About Pressure Boundary Leakage on Reactor Coolant Pump 2A Pipe Nozzle
ML15070A2522015-02-18018 February 2015
Pre-Submittal Public Meeting Final Slides on Risk-Informed Completion Times.
ML15042A4152015-02-11011 February 2015
Pre-Submittal Public Meeting Draft Slides on Risk- Informed Completion Times
ML14184B4112014-06-11011 June 2014
Nrc/Nei/Utility MTG 6/11/14
ML14149A5092014-04-23023 April 2014
4/23/14 Meeting Slide for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Re. Sig Tube Inspection
ML14098A1832014-04-0202 April 2014
4/2/2014 Meeting Slide for Bottom-Mounted Instrument (Bmi) Relief Request 52 Pre-Submittal Meeting
ML13309A7202013-11-0505 November 2013
Meeting Presentation for November 5, 2013 Public Meeting Regarding Incorporation of NEI 11-04 Into the QA Program at Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML13308B3322013-11-0404 November 2013
Meeting Presentation for November 4, 2013 Public Meeting Regarding Bmi Leakage
ML13308C3402013-11-0404 November 2013
SG Unit 3 Telephone Call
ML13025A2832013-01-29029 January 2013
NRC Comments on Draft Integrated Plans, Palo Verde
ML12311A0492012-09-18018 September 2012
Part 26 Public Meeting NEI Presentation Slides
ML12243A4352012-08-30030 August 2012
8/30/2012 Meeting RR 48 - Phased Array Ultrasonic Examination in Lieu of Radiography
ML12243A4382012-08-30030 August 2012
8/30/2012 Meeting - RR 48 UT Vs Rt Discussion
ML12243A4472012-08-30030 August 2012
8/30/2012 Meeting - RR 48 UT in Lieu of Rt for Nuclear Power Plant Applications
ML12157A2722012-06-11011 June 2012
5/31/2012 Summary of Telephone Conference with Licensees Regarding Near Term Task Force Recommendation 2.1 Seismic Reevaluations - Diablo Canyon, 1 and 2, San Onofre, Units 2 and 3, Columbia Generating Station, and Palo Verde, Units 1, 2, a
ML11188A0722011-07-0606 July 2011
NRC Meeting with NEI and Licensees June 28, 2011 Workshop Engineering Approach Rev F
2024-02-07
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML24038A1742024-02-0707 February 2024
Pre-submittal Meeting 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
ML24003A8532024-01-0303 January 2024
January 4, 2024 Presubmittal Meeting Presentation-Risk Informed Process for Evaluations (RIPE) License Amendment Request for Safety Injection Tank (SIT) LCO (EPID: L?2023?LRM-0108)
ML23296A0162023-10-20020 October 2023
October 20, 2023 Presubmittal Meeting Presentation - 1R24 Pressurizer Nozzle Repair - RR-70 (EPID: L?2023?LLR-0057)
ML23240A3232023-08-31031 August 2023
APS Presentation Slides for Pre-Submittal Meeting on 8/31/23, Alloy-600 Management Program Plan
ML23192A0102023-07-11011 July 2023
NRC RIPE 7-11-23 Public Meeting Presentation Slides
ML23144A0252023-05-25025 May 2023
APS Presentation Slides for Pre-Submittal Meeting on 5/25/23, Przr Surge Line
ML23093A0252023-04-30030 April 2023
April 5, 2023, Presubmittal Meeting Presentation - Containment Temperature and Safety Injection Tank Volume Requirements LAR
ML23055B0572023-03-0101 March 2023
March 1, 2023 Presubmittal Meeting Presentation - Request for Use of Mururoa V4F1 and MTH2 Supplied Air Suits (EPID: L?2023?LRM-0012)
ML22312A5952022-11-0808 November 2022
Independent Spent Fuel Storage Installation, Submittal of Annual Financial Reports 2021
ML22299A1812022-10-26026 October 2022
Presubmittal Meeting Presentation - License Amendment Request - Adoption of TSTF-107-A Separate Control Rods That Are Untrippable Versus Inoperable and Change to TS 3.1.5 Condition B (EPID: L?2021?LRM-0081)
ML22096A0052022-04-0606 April 2022
TSTF-487 LAR Pre-submittal Public Meeting Presentation Slides
ML22025A0012022-01-25025 January 2022
1/25/22 Pre-submittal Meeting Presentation Slides for RR-69 to Extend Containment Tendon Inspection by Three Months Beyond 2/8/22
ML21342A0502021-12-0808 December 2021
TSTF-567 LAR Pre-submittal Public Meeting Presentation Slides
ML21320A1032021-11-17017 November 2021
RIPE Exemption 11-17-21 Pre-submittal Public Meeting Presentation Slides
ML21278B0912021-10-0606 October 2021
Presubmittal Meeting with Arizona Public Service Company Regarding Relief Request No. 68 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 (EPID L-2021-LRM-0104) (Slides)
ML21243A5432021-09-0101 September 2021
Request for Partial Exemption from 10 CFR 50.62(c)(1) Risk-Informed Process for Evaluations (RIPE)
ML21194A2502021-08-10010 August 2021
RIC 2021 - Ai EPRI-Artificial Intelligence and Development at EPRI
ML21165A1832021-06-14014 June 2021
RR-67 6-16-21 Pre-Submittal Public Meeting Presentation Slides
ML21131A0132021-05-13013 May 2021
License Transfer from Pnm to SRP, 5-13-21 Pre-submittal Public Meeting Presentation Slides
ML21130A6462021-05-13013 May 2021
Pre-Submittal Meeting with NRC on May 13, 2021 Application for Transfer of Minority Interests in Palo Verde Nuclear Generating Station, Units 1 and 2 Subject to Expiring Leases
ML21055A8502021-02-24024 February 2021
Public Meeting Summary
ML21025A0032021-01-26026 January 2021
Risk-Informed Process for Evaluations (RIPE) - NEI Public Meeting Presentation Slides
ML21025A0042021-01-25025 January 2021
Risk-Informed Process for Evaluations (RIPE) - NRC Public Meeting Presentation Slides
ML21011A2752021-01-0606 January 2021
License Amendment Request (LAR) to Revise Containment Leakage Rate Testing Program Frequencies - NRC Pre-Submittal Meeting, January 6, 2021 (Presentation Slides)
ML20171A2352020-06-24024 June 2020
Inservice Testing - Supplemental Position Indication Relief Request - NRC Pre-Application Meeting - June 24, 2020
ML19060A2982019-03-0101 March 2019
Transmittal of Audit Presentation Slides Regarding License Amendment Request and Exemption Request to Support the Implementation of Framatome CE16HTP Fuel
ML17003A0762017-01-10010 January 2017
Regulatory Audit Report for the November 2-3, 2016, Audit at the Westinghouse Facility in Rockville, MD, for the License Amendment and Exemption Requests Associated with Next Generation Fuel (CAC Nos. MF8076-MF8081)
ML17003A0352017-01-0404 January 2017
Summary of Pre-Application Meeting with Arizona Public Service to Discuss a Proposed Second Emergency License Amendment Request to Revise Technical Specification 3.8.1, AC (Alternating Current) Sources - Operating, for Palo Verde Nuclear
ML17003A0332016-12-29029 December 2016
Enclosure 2 - APS Meeting Slides
ML17003A0862016-11-0303 November 2016
Enclosure 2 Slides Regulatory Audit Report for November 2-3, 2016
ML16253A4112016-09-0707 September 2016
Palo Verde Nuclear Generating Station Generic Letter 2004-02 - September 7, 2016
ML16083A4722016-03-24024 March 2016
NRC Subsequent Pre-Submittal Meeting Next Generation Fuel - Palo Verde, Units 1, 2, and 3
ML16014A1102016-01-20020 January 2016
Draft APS Slides for January 20, 2015, Public Meeting with APS Regarding Upcoming Next Generation Fuel License Amendment Request for Palo Verde, Units 1, 2, and 3
ML15348A0542015-12-15015 December 2015
Slides for December 17, 2015 Public Meeting with APS on Resolution of GL 2004-02
ML15244B2632015-08-27027 August 2015
Slides for Public Meeting with Arizona Public Service Company to Discuss License Amendment Request for Palo Verde Regarding Revised Methodology for Spent Fuel Pool Criticality Analysis
ML15236A1342015-08-26026 August 2015
Presentation Slides for Public Meeting with Arizona Public Service Generic Letter 2004-02 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML15159B2972015-06-0909 June 2015
Near-Term Task Force Recommendation 2.1 (R2.1) Seismic Hazard Evaluation - Arizona Public Service, Palo Verde Nuclear Generating Station Public Meeting - June 9, 2015
ML15156B3312015-06-0909 June 2015
Public Meeting Slides on R2.1 Seismic Hazard Re-Evaluation
ML15134A3592015-05-11011 May 2015
5/11/2015, Meeting Slide Regarding Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality Analysis
ML15126A2072015-05-11011 May 2015
Presentation Slides for Prelicensing Meeting with Arizon Public Service Company to Discuss License Amendment Request for Palo Verde, Units 1, 2, and 3,
ML15103A2882015-04-0909 April 2015
Presentation on Potential Relief Request About Pressure Boundary Leakage on Reactor Coolant Pump 2A Pipe Nozzle
ML15070A2522015-02-18018 February 2015
Pre-Submittal Public Meeting Final Slides on Risk-Informed Completion Times.
ML15042A4152015-02-11011 February 2015
Pre-Submittal Public Meeting Draft Slides on Risk- Informed Completion Times
ML14184B4112014-06-11011 June 2014
Nrc/Nei/Utility MTG 6/11/14
ML14149A5092014-04-23023 April 2014
4/23/14 Meeting Slide for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 Re. Sig Tube Inspection
ML14098A1832014-04-0202 April 2014
4/2/2014 Meeting Slide for Bottom-Mounted Instrument (Bmi) Relief Request 52 Pre-Submittal Meeting
ML13309A7202013-11-0505 November 2013
Meeting Presentation for November 5, 2013 Public Meeting Regarding Incorporation of NEI 11-04 Into the QA Program at Palo Verde Nuclear Generating Station, Units 1, 2, and 3
ML13308B3322013-11-0404 November 2013
Meeting Presentation for November 4, 2013 Public Meeting Regarding Bmi Leakage
ML13197A0952013-07-11011 July 2013
7/11/13 Meeting Slides - Implementation of STAR Program and Replacement of the 2/3 Cycle Mtc Measurement
2024-02-07
[Table view] |
Text
Palo Verde Nuclear Generating Station Generic Letter 2004-02 August 26th, 2015
Introductions
Tom Weber Department Leader Nuclear Regulatory Affairs
Background
- 4/15/2015 - PVAR 4644513 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel
- 6/10/2015 - Initial Public Meeting with NRC
- Beaver Valley Operating Experience with Microtherm
- Communication with the Industry
- Industry Testing of Microporous Insulation
- Extent of Condition 3
Microtherm Locations 4
Break Locations Reactor Pressure Vessel (RPV) Nozzle break locations Limiting Break Location Steam Generator Hot Leg Nozzle 5
Extent of LOCATION Unit 1 Unit 2 Unit 3 Cold Leg 1A, 1B, 2A, 2B RTD X X X Below RPV Nozzle X X X Condition RPV Cavity RPV ICIs Crossover 1A, 1B, 2A, 2B RCP X
X X
X X
X Nozzle X Crossover 1A, 1B, 2A, 2B SG Nozzle X Cold Leg 1A, 1B, 2A, 2B RPV Elbow X Red: Temp-Mat Impacting Existing Break Location (SG HL Nozzle)
Green: Temp-Mat Impacting New RPV Break Location Unit 3 Only 6
Analysis to date
- Primary success path is removal of Temp-Mat in the D-rings for current limiting break
- Microtherm ZOI (zone of influence) based on robustness of encapsulation
- Encapsulated Microtherm ZOI and restrained separation of pipe at RPV nozzle break limits Microtherm quantity to the local region of the break location
- RPV nozzle break - Temp-Mat generated to the Reactor Cavity will not transport to strainers based on very low flow velocity and upward vertical flow path of 18 to 23 feet
- Cold Leg RPV Elbow Temp-Mat is still being analyzed for impact (Unit 3 Only)
- Generated Microtherm assumed to transport to the strainers 7
Analysis to date (cont)
- Salem U2 Test 6 Head Loss conditions (with Min-K) bound Palo Verde with Microtherm for post-LOCA flow scenarios
- Comparative analysis indicates Palo Verde NPSH and structural limits should be bounded by existing SG HL Break location 8
Actions to finalize
- Confirm Removal of Temp-Mat from D-ring
- Confirm Removal of Temp-Mat from Unit 3 RPV Cold Leg Elbows
- Confirm impact of identified Temp-Mat and Microtherm for RPV on chemical effects
- Finalize LPSI pump failure to trip after Recirculation Actuation Signal (RAS)
Scenario
- Complete final review of assessment report 9
Summary
- A resolution path exists for D-ring and RPV nozzle break cases
- Confirmation of chemical effects and LPSI flow scenario items in process
- Open Strainer Area is expected to be comparable with original analysis
- Confirm removal of Temp-Mat in D-Ring
- Removal of RTD Temp-Mat (all 3 units)
- Removal of Crossover Piping Temp-Mat in Unit 3
- Confirm removal of Cold Leg RPV Elbows in Unit 3
We SAFELY and efficiently generate electricity for the long term 11
