Meeting Handouts from 05/30/2002 Meeting on Status of Fuel Performance, Control Rod Replacement, & Implementation of Approved Cents Code, at Palo Verde Nuclear Generating Station, Units 1, 2, & 3ML021510026 |
Person / Time |
---|
Site: |
Palo Verde |
---|
Issue date: |
05/30/2002 |
---|
From: |
Donohew J NRC/NRR/DLPM/LPD4 |
---|
To: |
|
---|
References |
---|
Download: ML021510026 (15) |
|
|
---|
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] |
Text
NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9- 1999)
TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed or hand-printed)by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed form, and the attachedcopy of meeting handout materials, will be sent to the Document Control Desk on the same day of the meeting; under no circumstances will this be done later than the working day after the meeting.
Do not include proprietarymaterials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 05/30/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-528, 50-529, and 50-530 Plant/Facility Name Palo Verde Nuclear Generating Station, Units 1, 2, and 3 TAG Number(s) (if available)
Reference Meeting Notice Meeting Notice dated May 2, 2002 Purpose of Meeting (copy from meeting notice) The licensee will provide the NRC staff with the status of fuel performance, control rod replacement, and imple mentation of the approved CENTS Code, at the units.
NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE Jack Donohew Senior Project Manager OFFICE Office of Nuclear Reactor Regulation DIVISION Division of Licensing Project Management BRANCH Project Directorate IV Distribution of this form and attachments:
Docket File/Central File PUBLIC NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER This form was designed using InForms
Nuclear Fuel Update Palo Verde Nuclear Generating Station May 30, 2002 Meeting with US NRC Review of 2001
- March 2001 Meeting with NRR
+ Approval of new MDNBR Limit
- Progress with Clad Performance
- Alloy A LFA Approved For 4 th Burn
- Zirlo Tech Spec Submitted I
Agenda Today
- Review of Unit 2 Cycle 11
+ CENTS Implementation & Licensing
- Integrated Clad Performance Strategy
- Update on CEA Investigation
+ Dry Cask Storage Update Unit 2 Cycle 11 Activities Incorporated in the Reload Safety Analyses 2
U2CK 1 Reload Analyses
+ Implementation of New MDNBR Limit
- Manufacturing Transition to Columbia
+ Implementation of Zirlo Clad & New LOCA Methodology
- Implementation of New CENTS AORs CENTS System Code Implementation & Licensing
CENTS Impiementation Plan
+ All UFSAR Chapter 15 Analyses
+ Two Events Remain In Progress
- Steam Generator Tube Rupture
- CEA Ejection Dose Consequences Steam Generator Tube Rupture
- Consequences Increase > Minimal
- Timing of Aux FW & ADV opening
- New Limiting SG Level
- Retain Current CESEC AOR Until CENTS Analysis Reviewed & Approved
- Consistent With RSG/PUR Submittal
CEA Ejection Dose Consequences
- Evaluating CENTS Applicability
- Retain Current CESEC AOR Until CENTS Implemented
- Will Not Impact RSG/PUR Submittal Palo Verde Integrated Clad Performance Strategy Review of Recent Capabilities U2 Uprate Corrosion Strategy 10
Integrated Fuel Clad Strateg~y
+ Primary System Chemistry
- Low Duty Core Designs 11 A Advanced Clad Alloys
- Full Batch Zirlo starting U2C1 1 (Spring 2002)
- Alloy A LTA in U3C10 (Spring 2003)
Primary Chemistry
- Additional RCS Cleaning at EOC Shutdown
- Early Lithium Injection During Startups
+ Elevated-Coordinated Lithium Strategy
- Currently 7.1 pH
- Inspection Ul R1 0 (Fall 2002)
- Gradual Increase to > 7.2 pH 13 Higher Order Modeling
+ Uncertainty in Behaviors = Multiple Models
+ Steaming Rate Function in Design Tools
- U3C9 Benchmark
- Pin x Pin Colorset and Coarse Mesh Octant
- Oxide and FDI for all Clads 14 7
Low Duty Core Designs
- 104 vs 96 Assemblies
- U2 Uprate Corrosion Strategy
- 3% Power and 22 F Coolant Temperature
- Zirlo Clad
- Re-design Lattice Pattern 8
Palo Verde CEA ReplacemenR Update on CEA Investigation 17 Review of CEA Replacement
- CEA Finger Failures Observed - all Units
- Significant Cracks in High Fluence CEAs
- Boron Loss in U1 Lead Group
- Some Medium Fluence CEA Cracking
- U2R8 CEA Found Cracked (Jan. 2002)
+ All Full Length CEAs Replaced
- Two Different Tip Designs
- Replaced by Design with Smallest Pellet 9
Apparent Cause of Failures
- Irradiation Sensitized Inconel
- Swelling-induced Strain
- Less than Adequate Design Testing
- Feltmetal Properties Unverified at High Duty
- Pellet-Feltmetal Interaction
+ Lifetime Predictive Software
- Models Not Fully Benchmarked 11)
Remaining Actions
+ Determine Conservative Estimate of Life
- 2 Cycle Fingers OK
- Possible YGN Inspections
- Possible Hot Cell Exams
- 2x1 021 n/cm 2 Threshold?
+ CEA re-Design for the Future 20 10
Palo Verde Dry Cask Storage Plan Overview 21 11
Project Schedule
- Concrete Cask fab completed 3/31/02
- First Canister delivery 6/28/02
- ISFSI Construction complete 8/1.9/02
- Security features installed 9115/02
+ Dry run practice begins 8/1/02
+ NRC dry run observations mid Noverr iber
- First system on the pad by Christmas i I
Palo Verde Dry Cask Storage Principal Components (Cut-away View)
Transportable Storage Canister Dimensions:
Transfer cask Ht. 16 ft. 11 in.
Dia. 7 ft. 1 in.
Loaded canister Ht. 15 ft. 11 in.
Dia. 5 ft. 7 in.
vCC Ht. 18 ft. 10 in.
Dia. 11 ft. 4 in.
Weight:
Transfer cask 60 tons Loaded canister 35 tons vCC 119 tons Loaded system 154 tons