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| {{#Wiki_filter:Palo Verde Nuclear Generating Station Generic Letter 2004-02 September 7, 2016 Mike Dilorenzo Department Leader Nuclear Regulatory Affairs Agenda Introductions Background Overview of Results Plant Configuration Results of Analysis Path Forward 2 Background 12/18/2013 - APS submitted Revision 2 to Supplemental Response to NRC Generic Letter 2004-02 (Option 2A) 4/15/2015 - Condition Report 15-01860 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel 6/10/2015 - Initial Public Meeting with NRC 8/26/2015 - Follow up Public Meeting with NRC 12/17/2015 - Follow up Public Meeting with NRC 4/30/2016 - Unit 1 Inspections 3 Overview of Results Palo Verde remains a "low fiber plant" Transported fiber quantities from D-ring and RPV nozzle breaks are within the amounts used in Palo Verde head loss testing Analyzed Microtherm Impact NPSH and structural limits are satisfied (based on comparative analysis) Open surface area precludes typical high headloss impact of Microtherm on fiber beds Analyzed Temp-Mat Impact Fines assumed to transport Low flow velocity / vertical flow path inhibits small & large piece transport Open surface area remains NPSH and structural limits are satisfied (based on comparative analysis) 4 5 Microtherm Locations Plant Configuration Temp-Mat Plant Configuration Original Limiting Break Location Steam Generator Hot Leg Nozzle Reactor Pressure Vessel (RPV) Hot Leg Nozzle Break Location 6 Plant Configuration 7 LOCATION Unit 1 Unit 2 Unit 3 Planned Disposition RPV (Microtherm & Temp-Mat) X X X Addendum RPV Cavity (Microtherm & Temp-Mat) X X X Addendum RPV ICIs (Temp-Mat) X X X Addendum Feedwater / SDC Lines (Nukon) Comp 2017 2016 Remove Cold Leg 1A, 1B, 2A, 2B RTD (Temp-Mat) Comp Comp 2016 Remove Crossover 10A, 1B, 2A, 2B RCP & SG Nozzles (Temp-Mat) N/A N/A 2016 Remove Cold Leg 1A, 1B, 2A, 2B RPV Elbow (Temp-Mat) N/A N/A 2016 Remove RCP Stops 1A, 1B, 2A, 2B (Temp-Mat) N/A N/A 2016 Remove Results of Analysis Debris Generation -Microtherm zone of influence (ZOI) based on robustness of encapsulation -Temp-Mat ZOI is from NEI 04-07 Safety Evaluation -RPV nozzle break debris quantity estimates account for restrained separation of pipe at RPV nozzle breaks - Utilizing information from BWR Owners Group Utility Resolution Guidance Debris Transport -RPV nozzles breaks All destroyed Microtherm is considered to transport to the strainer All Temp-Mat Fines, including from erosion, are considered to transport from Reactor Cavity to strainers Small and large Temp-Mat pieces generated in the Reactor Cavity will not transport to strainers based on turbulent kinetic energy and low flow velocity in upward vertical flow path of 24 to 42 feet (for all flow scenarios) 8 Results of Analysis (cont) Chemical Effects Load -Estimated using WCAP-16530-NP spreadsheet -Palo Verde test used higher loads than required by analysis of record -Salem U2 Test 6 (S2T6) used in comparative analyses for headloss D-ring break -Normalized load (lbm/ft2) is under 70% of test of record and less than 55% of S2T6 RPV nozzle breaks -Normalized load (lbm/ft2) is slightly under (98% of) test of record and less than 80% of S2T6 9 Results of Analysis (cont) Head Loss / NPSH -Comparative analysis with S2T6 indicates Palo Verde NPSH and structural limits are not challenged S2T6 fiber, particulate, Min-K and chemical effects loads bound Palo Verde with Microtherm debris quantities S2T6 had no open area - fully developed debris bed with a thickness of 0.3 inches Palo Verde retains open screen area Differences in approach velocities compensated by open strainer area Updated strainer structural capacity, based on ASME NF analysis and allowable stress limits, results in minimum headloss margin of 2.2 ft-water for governing break 10 Summary Analysis of both the original D-ring break location and the RPV nozzle break cases have favorable results Fiber inspection & removal will continue for the following outages -Unit 3R19 (Fall 2016) -Unit 2R20 (Spring 2017) -Unit 1R20 (Fall 2017) -Unit 3R20 (Spring 2018) -Unit 2R21 (Fall 2018) -Unit 1R21 (Spring 2019) Addendum to the Supplemental APS Response to GL 2004-02 (November 2016) 11 12 We SAFELY and efficiently generate electricity for the long term}} | | {{#Wiki_filter:Palo Verde Nuclear Generating Station Generic Letter 2004 |
| | -02 September 7, 2016 Mike Dilorenzo Department Leader Nuclear Regulatory Affairs |
| | |
| | Agenda Introductions |
| | |
| | ===Background=== |
| | Overview of Results Plant Configuration Results of Analysis Path Forward 2 |
| | |
| | ===Background=== |
| | 12/18/2013 |
| | - APS submitted Revision 2 to Supplemental Response to NRC Generic Letter 2004-02 (Option 2A) 4/15/2015 |
| | - Condition Report 15 |
| | -01860 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel 6/10/2015 |
| | - Initial Public Meeting with NRC 8/26/2015 |
| | - Follow up Public Meeting with NRC 12/17/2015 |
| | - Follow up Public Meeting with NRC 4/30/2016 |
| | - Unit 1 Inspections 3 |
| | Overview of Results Palo Verde remains a "low fiber plant" Transported fiber quantities from D |
| | -ring and RPV nozzle breaks are within the amounts used in Palo Verde head loss testing Analyzed Microtherm Impact NPSH and structural limits are satisfied (based on comparative analysis) Open surface area precludes typical high headloss impact of Microtherm on fiber beds Analyzed Temp |
| | -Mat Impact Fines assumed to transport Low flow velocity / vertical flow path inhibits small & large piece transport Open surface area remains NPSH and structural limits are satisfied (based on comparative analysis) 4 5 Microtherm Locations Plant Configuration Temp-Mat Plant Configuration Original Limiting Break Location Steam Generator Hot Leg Nozzle Reactor Pressure Vessel (RPV) Hot Leg Nozzle Break Location 6 |
| | Plant Configuration 7 LOCATION Unit 1 Unit 2 Unit 3 Planned Disposition RPV (Microtherm & Temp |
| | -Mat) X X X Addendum RPV Cavity (Microtherm & Temp |
| | -Mat) X X X Addendum RPV ICIs (Temp |
| | -Mat) X X X Addendum Feedwater / SDC Lines (Nukon) |
| | Comp 2017 2016 Remove Cold Leg 1A, 1B, 2A, 2B RTD (Temp-Mat) Comp Comp 2016 Remove Crossover 10A, 1B, 2A, 2B RCP & SG Nozzles (Temp |
| | -Mat) N/A N/A 2016 Remove Cold Leg 1A, 1B, 2A, 2B RPV Elbow (Temp |
| | -Mat) N/A N/A 2016 Remove RCP Stops 1A, 1B, 2A, 2B (Temp-Mat) N/A N/A 2016 Remove Results of Analysis Debris Generation |
| | -Microtherm zone of influence (ZOI) based on robustness of encapsulation |
| | -Temp-Mat ZOI is from NEI 04-07 Safety Evaluation |
| | -RPV nozzle break debris quantity estimates account for restrained separation of pipe at RPV nozzle breaks |
| | - Utilizing information from BWR Owners Group Utility Resolution Guidance Debris Transport |
| | -RPV nozzles breaks A ll destroyed Microtherm is considered to transport to the strainer All Temp-Mat Fines, including from erosion, are considered to transport from Reactor Cavity to strainers Small and large Temp-Mat pieces generated in the Reactor Cavity will not transport to strainers based on turbulent kinetic energy and low flow velocity in upward vertical flow path of 24 to 42 feet (for all flow scenarios) 8 Results of Analysis (cont) Chemical Effects Load |
| | -Estimated using WCAP-16530-NP spreadsheet |
| | -Palo Verde test used higher loads than required by analysis of record -Salem U2 Test 6 (S2T6) used in comparative analyses for headloss D-ring break |
| | -Normalized load (lbm/ft 2) is under 70% of test of record and less than 55% of S2T6 RPV nozzle breaks |
| | -Normalized load (lbm/ft |
| | : 2) is slightly under (98% of) test of record and less than 80% of S2T6 9 Results of Analysis (cont) Head Loss / NPSH -Comparative analysis with S2T6 indicates Palo Verde NPSH and structural limits are not challenged S2T6 fiber, particulate, Min |
| | -K and chemical effects loads bound Palo Verde with Microtherm debris quantities S2T6 had no open area |
| | - fully developed debris bed with a thickness of 0.3 inches Palo Verde retains open screen area Differences in approach velocities compensated by open strainer area Updated strainer structural capacity, based on ASME NF analysis and allowable stress limits, results in minimum headloss margin of 2.2 ft-water for governing break 10 Summary Analysis of both the original D |
| | -ring break location and the RPV nozzle break cases have favorable results Fiber inspection & removal will continue for the following outages |
| | -Unit 3R19 (Fall 2016) |
| | -Unit 2R20 (Spring 2017) |
| | -Unit 1R20 (Fall 2017) |
| | -Unit 3R20 (Spring 2018) |
| | -Unit 2R21 (Fall 2018) |
| | -Unit 1R21 (Spring 2019) |
| | Addendum to the Supplemental APS Response to GL 2004-02 (November 2016) 11 12 We SAFELY and efficiently generate electricity for the long term}} |
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MONTHYEARML16011A0582016-01-21021 January 2016 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 ML16253A4112016-09-0707 September 2016 Palo Verde Nuclear Generating Station Generic Letter 2004-02 - September 7, 2016 Project stage: Other 2016-01-21
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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 - 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 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 - 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 2024-09-20
[Table view] |
Text
Palo Verde Nuclear Generating Station Generic Letter 2004
-02 September 7, 2016 Mike Dilorenzo Department Leader Nuclear Regulatory Affairs
Agenda Introductions
Background
Overview of Results Plant Configuration Results of Analysis Path Forward 2
Background
12/18/2013
- APS submitted Revision 2 to Supplemental Response to NRC Generic Letter 2004-02 (Option 2A) 4/15/2015
- Condition Report 15
-01860 documents that APS failed to identify and evaluate Microtherm on the Reactor Vessel 6/10/2015
- Initial Public Meeting with NRC 8/26/2015
- Follow up Public Meeting with NRC 12/17/2015
- Follow up Public Meeting with NRC 4/30/2016
- Unit 1 Inspections 3
Overview of Results Palo Verde remains a "low fiber plant" Transported fiber quantities from D
-ring and RPV nozzle breaks are within the amounts used in Palo Verde head loss testing Analyzed Microtherm Impact NPSH and structural limits are satisfied (based on comparative analysis) Open surface area precludes typical high headloss impact of Microtherm on fiber beds Analyzed Temp
-Mat Impact Fines assumed to transport Low flow velocity / vertical flow path inhibits small & large piece transport Open surface area remains NPSH and structural limits are satisfied (based on comparative analysis) 4 5 Microtherm Locations Plant Configuration Temp-Mat Plant Configuration Original Limiting Break Location Steam Generator Hot Leg Nozzle Reactor Pressure Vessel (RPV) Hot Leg Nozzle Break Location 6
Plant Configuration 7 LOCATION Unit 1 Unit 2 Unit 3 Planned Disposition RPV (Microtherm & Temp
-Mat) X X X Addendum RPV Cavity (Microtherm & Temp
-Mat) X X X Addendum RPV ICIs (Temp
-Mat) X X X Addendum Feedwater / SDC Lines (Nukon)
Comp 2017 2016 Remove Cold Leg 1A, 1B, 2A, 2B RTD (Temp-Mat) Comp Comp 2016 Remove Crossover 10A, 1B, 2A, 2B RCP & SG Nozzles (Temp
-Mat) N/A N/A 2016 Remove Cold Leg 1A, 1B, 2A, 2B RPV Elbow (Temp
-Mat) N/A N/A 2016 Remove RCP Stops 1A, 1B, 2A, 2B (Temp-Mat) N/A N/A 2016 Remove Results of Analysis Debris Generation
-Microtherm zone of influence (ZOI) based on robustness of encapsulation
-Temp-Mat ZOI is from NEI 04-07 Safety Evaluation
-RPV nozzle break debris quantity estimates account for restrained separation of pipe at RPV nozzle breaks
- Utilizing information from BWR Owners Group Utility Resolution Guidance Debris Transport
-RPV nozzles breaks A ll destroyed Microtherm is considered to transport to the strainer All Temp-Mat Fines, including from erosion, are considered to transport from Reactor Cavity to strainers Small and large Temp-Mat pieces generated in the Reactor Cavity will not transport to strainers based on turbulent kinetic energy and low flow velocity in upward vertical flow path of 24 to 42 feet (for all flow scenarios) 8 Results of Analysis (cont) Chemical Effects Load
-Estimated using WCAP-16530-NP spreadsheet
-Palo Verde test used higher loads than required by analysis of record -Salem U2 Test 6 (S2T6) used in comparative analyses for headloss D-ring break
-Normalized load (lbm/ft 2) is under 70% of test of record and less than 55% of S2T6 RPV nozzle breaks
-Normalized load (lbm/ft
- 2) is slightly under (98% of) test of record and less than 80% of S2T6 9 Results of Analysis (cont) Head Loss / NPSH -Comparative analysis with S2T6 indicates Palo Verde NPSH and structural limits are not challenged S2T6 fiber, particulate, Min
-K and chemical effects loads bound Palo Verde with Microtherm debris quantities S2T6 had no open area
- fully developed debris bed with a thickness of 0.3 inches Palo Verde retains open screen area Differences in approach velocities compensated by open strainer area Updated strainer structural capacity, based on ASME NF analysis and allowable stress limits, results in minimum headloss margin of 2.2 ft-water for governing break 10 Summary Analysis of both the original D
-ring break location and the RPV nozzle break cases have favorable results Fiber inspection & removal will continue for the following outages
-Unit 3R19 (Fall 2016)
-Unit 2R20 (Spring 2017)
-Unit 1R20 (Fall 2017)
-Unit 3R20 (Spring 2018)
-Unit 2R21 (Fall 2018)
-Unit 1R21 (Spring 2019)
Addendum to the Supplemental APS Response to GL 2004-02 (November 2016) 11 12 We SAFELY and efficiently generate electricity for the long term