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| | 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 |
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| =Text= | | =Text= |
| {{#Wiki_filter:Palo Verde Nuclear Generating Station Generic Letter 2004-02August 26 th , 2015 IntroductionsTom Weber Department LeaderNuclear Regulatory Affairs | | {{#Wiki_filter:Palo Verde Nuclear Generating Station Generic Letter 2004-02 August 26th, 2015 |
| | |
| | ===Introductions=== |
| | Tom Weber Department Leader Nuclear Regulatory Affairs |
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| ===Background=== | | ===Background=== |
| *12/18/2013 -APS submitted Revision 2 to Supplemental Response to NRC Generic Letter | | * 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 |
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| |
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| 2004-02*4/15/2015 -PVAR 4644513 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel
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| *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
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| Microtherm Locations 4 | | Microtherm Locations 4 |
| Break LocationsLimiting Break Location Steam Generator Hot Leg NozzleReactor Pressure Vessel (RPV) Nozzle break locations 5
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| 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 CavityXXX RPV ICIsXXXCrossover 1A, 1B, 2A, 2B RCP Nozzle XCrossover 1A, 1B, 2A, 2B SG Nozzle XCold Leg 1A, 1B, 2A, 2B RPV Elbow X Unit 3 Only Analysis to date
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| *Debris Generation
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| -Primary success path is removal of Temp-Mat in the D-rings for current limiting break
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| -Microtherm ZOI (zone of influence) based on robustness of
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| encapsulation | | Break Locations Reactor Pressure Vessel (RPV) Nozzle break locations Limiting Break Location Steam Generator Hot Leg Nozzle 5 |
| -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 | | 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 |
| -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 | | X X |
| *Cold Leg RPV Elbow Temp-Mat is still being analyzed for impact (Unit 3 Only) | | X X |
| -Generated Microtherm assumed to transport to the strainers 7 | | 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) |
| Analysis to date (cont)*Industry Testing / NPSH
| | Green: Temp-Mat Impacting New RPV Break Location Unit 3 Only 6 |
| -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
| | Analysis to date |
| Actions to finalize
| | * Debris Generation |
| *Confirm Removal of Temp-Mat from D-ring
| | - Primary success path is removal of Temp-Mat in the D-rings for current limiting break |
| *Confirm Removal of Temp-Mat from Unit 3 RPV Cold Leg Elbows
| | - Microtherm ZOI (zone of influence) based on robustness of encapsulation |
| *Confirm impact of identified Temp-Mat and
| | - 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 |
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| Microtherm for RPV on chemical effects
| | Analysis to date (cont) |
| *Finalize LPSI pump failure to trip after Recirculation Actuation Signal (RAS) | | * 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 |
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| |
|
| Scenario*Complete final review of assessment | | 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 |
|
| |
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| report 9 Summary*A resolution path exists for D-ring and RPV nozzle break cases
| | Summary |
| -Confirmation of chemical effects and LPSI flow scenario items in process | | * A resolution path exists for D-ring and RPV nozzle break cases |
| -Open Strainer Area is expected to be comparable | | - 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 |
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| with original analysis
| | We SAFELY and efficiently generate electricity for the long term 11}} |
| *Confirm removal of Temp-Mat in D-Ring
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| -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 11We SAFELY and efficientlygenerate electricity for the long term}}
| |
Letter Sequence Meeting |
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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
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24262A1052024-09-20020 September 2024 Pre-Submittal Presentation Slides - 1R25 Pzr Nozzle Life of Repair - Relief Request 73 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML24236A7032024-08-22022 August 2024 Pre-Submittal Meeting Slides to Support August 29, 2024 Aps/Westinghouse Thermal Design Procedure (Wtdp) Meeting ML24212A3392024-08-0101 August 2024 August 1, 2024, Public Meeting on Potential Palisades Nuclear Plant Restart Presentation ML24192A3262024-07-12012 July 2024 Licensee Slides to Support Pre-Submittal Meeting – Relief Request 71 Slides ML24192A3402024-07-12012 July 2024 Licensee to Support Pre-Submittal Meeting - Relief Request 72 Slides ML24275A2332024-06-28028 June 2024 APS Slides Supporting Preapplication Meeting Regarding Safety Injection Tank Pressure Band ML24155A2112024-06-0707 June 2024 VRR-02: Exercise Test Frequency Reduction (Slides) ML24155A2122024-06-0707 June 2024 VRR-03: SOV Test Criteria (Slides) ML24038A1742024-02-0707 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 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, 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 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 ML13308C3402013-11-0404 November 2013 SG Unit 3 Telephone Call 2024-09-20
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24262A1052024-09-20020 September 2024 Pre-Submittal Presentation Slides - 1R25 Pzr Nozzle Life of Repair - Relief Request 73 for Palo Verde Nuclear Generating Station, Units 1, 2, and 3 ML24236A7032024-08-22022 August 2024 Pre-Submittal Meeting Slides to Support August 29, 2024 Aps/Westinghouse Thermal Design Procedure (Wtdp) Meeting ML24212A3392024-08-0101 August 2024 August 1, 2024, Public Meeting on Potential Palisades Nuclear Plant Restart Presentation ML24192A3262024-07-12012 July 2024 Licensee Slides to Support Pre-Submittal Meeting – Relief Request 71 Slides ML24192A3402024-07-12012 July 2024 Licensee to Support Pre-Submittal Meeting - Relief Request 72 Slides ML24275A2332024-06-28028 June 2024 APS Slides Supporting Preapplication Meeting Regarding Safety Injection Tank Pressure Band ML24155A2112024-06-0707 June 2024 VRR-02: Exercise Test Frequency Reduction (Slides) ML24155A2122024-06-0707 June 2024 VRR-03: SOV Test Criteria (Slides) ML24038A1742024-02-0707 February 2024 Pre-submittal Meeting Slides ML24019A1512024-01-22022 January 2024 Slides - 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Ai EPRI-Artificial Intelligence and Development at EPRI ML21165A1832021-06-14014 June 2021 RR-67 6-16-21 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 ML21131A0132021-05-13013 May 2021 License Transfer from Pnm to SRP, 5-13-21 Pre-submittal Public Meeting Presentation Slides 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 - 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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 2024-09-20
[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