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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
Nuclear Fuel Update Palo Verde Nuclear Generating Station November 16, 2006 Meeting with US NRC 1
VERDE PAL O
Nuclear Fuel Management Michael E. Powell, DR Nuclear Fuel Management Yovan Lukic, Principal Engr. Burton A. Grabo, PA Nuclear Fuel Management Nuclear Fuel Management Kathleen C. Parrish, TMA Nuclear Fuel Management Kevin Graham, DL John Hazelbaker, MGR Robert Bandera, DL Nuclear Fuel Services NFM Procurement Nuclear Fuel Analysis Vacant SL Thomas C. Cannon, SL Reactor Engineering Reload Analysis Brian J. Hansen, SL Craig A. Hasson, SL Dry Cask Storage Transient Analysis Rick L. Huffman, SL Fuel Services Jeffrey S. Schmidt, SL Nuclear Analysis 2
VERDE PAL O
Review of 2005-2006 December 2004 Meeting with NRR SG Replacement & Power Uprate Dry Cask Storage Successes SIMULATE Implementation Augmented AORs New Top Grid Design New CEAs & LFA Projects 3
VERDE PAL O
Agenda Today CEA Replacement Dual LFA Program Fuel Performance Dry Cask Storage Update Planned License Submittals 4
VERDE PAL O
CEA Replacement 5
VERDE PAL O
Review of CEA History Felt Metal Wrapped Pellets in Tips CEA Clad Failures Observed - 2001
- Cracks in High Fluence CEA Tips
- Root Cause - IASCC, Inadequate Testing All Full Length CEAs Replaced
- Replaced with Small Pellet Design Lifetime Software Abandoned 6
VERDE PAL O
Determination of New Lifetime Inspection versus Replacement Monitored YGN Inspections
- Vendor Adjusted Software
- Inconel IASCC Threshold Need New CEAs for Fall 2008 7
VERDE PAL O
Design of Future CEAs Want:
- Industry Standard AgInCd
- Extended Tip Region CEDM Weight Restrictions
- AgInCd Tip Region
- Boron Carbide for Remainder Lifetime
- ~20 EFPY Design Lifetime
- ~12 EFPY Experience Base (Hot Cell)
- ~18 EFPY Experience Base (PIE) 8 VERDE PAL O
Analysis & Licensing Impacts AgInCd Tip 75% Worth (vs. 90%) of B4C CEA Misoperation Events Bounded Scram Reactivity Curves Have Margin LOF & SS/SR Being Reanalyzed Tech Spec 4.2.2 Needs Revision 9
VERDE PAL O
Dual LFA Program 10 VERDE PAL O
Specific Fuel Design Goals Materials for Higher Burnup/Duty
- Cladding Oxidation
- Dimensional Stability Preserving/Increasing Operating Margins
- Minimize CRUD
- Increase Thermal Margin Improve Fuel Utilization Overall Robust Design for Flawless Fuel 11 VERDE PAL O
Lead Fuel Assembly Program Fuel Contract Timeline LFAs Needed to Demonstrate New Design
- Observe Performance in Both PV Duty Cycles
- 8 Assembly, 3 Fuel Cycle LFA Programs AREVA and Westinghouse Designs
- M5 (AREVA) and Optimized Zirlo (WEC)
- Mixing Vane Grids and IFMs in Spans 8 & 9
- Gadolinia (AREVA) and IFBA or Gd (WEC) BAs 12 VERDE PAL O
Analysis & Licensing Strategy Explicitly Model LFAs in Core Physics Model Maintain Within > 5% of Limiting Assembly Rod Burnup Will Remain < 60,000 MWD/T Vendors Perform Mechanical, Thermal Hydraulic &
LOCA Analyses
- AREVA to Assure Non-Limiting
- WEC to Assure Compatibility APS Performs Standard Reload Safety Analyses 13 VERDE PAL O
Analysis & Licensing Strategy (continued)
Safety Limits Preserved by Maintaining LFAs non-Limiting Transient Analyses Explicitly Validated COLSS & CPC Setpoints Explicitly Calculated 10CFR50.46 Exemption for M5 Required
- Expect Exemption for Optimized Zirlo Evaluating Need for Tech Spec Changes 14 VERDE PAL O
4.2.1 Fuel Assemblies Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff approved codes and methods and shown by tests or analyses to comply with all fuel safety design bases A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions Other cladding material may be used with an approved exemption.
15 VERDE PAL O
2.0 SAFETY LIMITS (SLs) 2.1.1.1 In MODES 1 and 2, Departure from Nucleate Boiling Ratio (DNBR) shall be maintained at > 1.34.
2.1.1.2 In MODES 1 and 2, the peak fuel centerline temperature shall be maintained <
5080°F (decreasing by 58°F per 10,000 MWD/MTU for burnup and adjusting for burnable poisons per CENPD-382-P-A).
16 VERDE PAL O
Palo Verde Fuel Performance 17 VERDE PAL O
Fuel Clad Performance Clad Performance in Uprate Conditions High Burnup Fuel Performance 18 VERDE PAL O
Clad Performance in Uprate Conditions o
3% Power and ~4 F Inlet Temperature New Steam Generators Increased Clad Oxidation Increased Steaming Rates o
- Each 1 F or 1% Power is Worth 10% Steaming Rate
- Higher Source Term from New Steam Generators
- CRUD & AOA Risk 19 VERDE PAL O
Integrated Clad Performance Strategy Advanced Clad Alloy Primary Chemistry CRUD and Oxide Software Three Enrichment Lattice Designs Long Range Fuel Inspection Plan 20 VERDE PAL O
The Two Duty Cycles Typical (U2C13) Core Design Fresh 1x burned 2x burned Reinserts 21 VERDE PAL O
ZIRLOTM Clad Westinghouse Low Tin Zirconium Based Alloy Protect High Duty 2 Cycle Assemblies
- First Implementation in Unit 2 Cycle 11 Licensing Limitations
- Fuel Duty Index & Maximum Oxide Thickness
- Vendor Oxide Software for Core Design Assessment 2R11, 2R12 & 2R13 Inspection Results
- Performance as Expected 22 VERDE PAL O
3 Enrichment Lattice Design Protect High Duty First Burn Assemblies
- First Implementation in Unit 2 Cycle 12 Design Concept - Balance Power & Flow
- In-House Designed Based on APS CRUD Model
- Three Enrichments, Four Pin Types Inspection Results
- 2R12 - No CRUD
- 2R13 - Threshold CRUD 23 VERDE PAL O
Sample Lattice Comparison Previous - 64 Er New - 64 Er 4.05 w/o 4.29 w/o 3.75 w/o 3.99 w/o 3.75 w/o Er 3.79 w/o 3.79 w/o Er 24 VERDE PAL O
Comparison of Average Crud Thickness - Predicted 6.95 7
New Lattice A v e ra g e C ru d 6 Design, Current 5 Source Term T h ic k n e s s in W o rs t 4 2.58 L u m p ed Ch an n el 3
1.25 2 0.5 (m ic ro n s ) 1 0
U2C9 U3C9 U2C11 U2C12 Unit and Cycle 25 VERDE PAL O
High Burnup Fuel Performance High Burnup Fuel Failure Trend Loose Top Grid Cells Top Grid Re-Design 26 VERDE PAL O
Flawless Fuel New Agreement with Westinghouse
- Identify and Investigate All Failures
- Incentive for Flawless Fuel
- Reconstitute Failed Assemblies Sipping in Containment UT in Spent Fuel Pool 27 VERDE PAL O
High Burnup Fuel Failure Trend Mid 90s, Clean Cores Cycle After Cycle Ten Failed First Burn Pins in U2C9 One Failed End Cap Weld (U1C9)
Nine Indications Starting with U2C9 Five of Nine Cycles with 1 or 2 Indications Three Identified Grid-Rod Fretting Failures No Current Operating Failures 28 VERDE PAL O
Loose Top Grid Cells PV1P Fabrication Campaign Root Causes
- Bias in Grid Construction Tolerances
- Force-Fit of 20 mil Oversize Guide Tube
- Rod Pushing Table Mis-Alignment
- Weaknesses in Inspection/QA Process 29 VERDE PAL O
Top Grid Re-Design Zirc-4 to Inconel 625 Wavy strip to Straight Strip Cantilever Spring Cut-out Double Back-up Arch Accommodation of Expanded Guide Tube Grid to Guide Tube Attachment Change to Top Nozzle (UEF) 30 VERDE PAL O
Dry Fuel Storage Update ISFSI in Production 4 Years 47 Casks on the Pads Doses Consistently Under 50 mR Need NAC Amendment #5 12/07 31 VERDE PAL O
Planned License Submittals 32 VERDE PAL O
Planned License Submittals TS 3.1.6 Shutdown CEA Insertion Limits (2006)
TS 5.6.5 Core Operating Limits Report (Summer 2007) 10CFR50.46 Exemption for M5 (Summer 2007)
TS 2.1.1 Fuel Safety Limits (Summer 2007)
TS 4.2.2 CEA Design (Fall 2007)
Revised Inlet Flow Uncertainties (Fall 2007)
Potential CEA Ejection with RAVE Methodology (2008) 33 VERDE PAL O
Shutdown CEA Insertion Limits Current T.S. Allows Insertion to 144.75 Withdrawn Safety Analysis Only Covers Insertion to 147.75
- Sufficient Additional Shutdown Margin Verified
- Guide Tube Wear Program Controlled to 147.75 Shutdown Margin is Monitored per Core Data Book T.S. 3.1.6 rewritten to 147.75 withdrawn Submitted to NRC Summer 2006 (Requested 6/07) 34 VERDE PAL O
Core Operating Limits Report Inconsistent CEA Drop Reference Currently Processing Changes
- Remove CESSAR References
- Add 3990 MW Power Uprate References
- Add Topical Report of 2nd Tier References Expected Submittal Date: Summer 2007 35 VERDE PAL O
M5 Clad Exemption Fall 2008 Insertion of AREVA LFAs M5 Already in Use M5 Not Listed in 10CFR50.46 Expected Submittal Date: Summer 2007 36 VERDE PAL O
TS 2.1.1 Safety Limits Potential TS Submittal to Allow for LFAs TS 2.1.1.1 DNBR
- Allow for Alternate CHF Correlation TS 2.1.1.2 Centerline Melt Temperature
- Allow for Alternate Burnable Absorbers Potential Submittal Date: Summer 2007 37 VERDE PAL O
TS 4.2.2 CEA Design Tech Spec 4.2.2 states:
The control section for the full strength CEAs shall be boron carbide with Inconel Alloy 625 cladding Needs to include AgInCd Expected Submittal Date: Fall 2007 38 VERDE PAL O
Revised Inlet Flow Uncertainties PV DNBR Limit Allows Statistical Combination of Inlet Flow Distribution Uncertainties
- Within DNBR Limit or via Deterministic Penalties Re-Analysis of Experimental Data
- Reduced Uncertainties
- Reduced DNBR Penalties Potential Submittal Date: Fall 2007 39 VERDE PAL O
CEA Ejection with RAVE Current CEA Ejection AOR Precludes Fresh Fuel Under Lead Bank Considering RAVE Analysis
- Core Design Flexibility
- Improves Worth for Axial Control
- Margin for New Criteria Potential Submittal Date: 2008 40 VERDE PAL O