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MONTHYEARML15134A3592015-05-11011 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 Project stage: Request ML15286A0282015-10-23023 October 2015 Summary of Presubmittal Meeting with Arizona Public Service Company to Discuss Revised Methodology for Spent Fuel Pool Criticality Analysis and Associated Technical Specification Changes for Palo Verde, Units 1, 2, and 3 (CAC MF6600-MF6602) Project stage: Meeting 2015-10-23
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Category:Meeting Briefing Package/Handouts
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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. 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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. 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[Table view] |
Text
Pre-Submittal Meeting for Palo Verde Unit 1, 2, and 3 Updated Spent Fuel Pool Criticality Analysis May 11, 2015
Purpose
- Present and discuss planned licensing changes
- Update spent fuel pool (SFP) criticality analysis
- Add neutron absorbing inserts to SFP racks 2
Objectives
- Updated criticality analysis will
- Provide basis for replacing non-conservative Technical Specification (TS) caused by missed power uprate impact
- Include Next Generation Fuel (NGF)
- Account for reactivity effects of integral fuel burnable absorber (IFBA)
- Maintain full core offload capability 3
Borated Aluminum Inserts
- Additional reactivity hold down is planned to meet 10 CFR 50.6850 68 and maintain full core offload capability
- Th Thermall h hydraulic, d li seismic, i i structural, t t l and d
pool cooling calculations will be updated as needed
- Add a coupon surveillance program to monitor material performance 4
TS Changes
- Incorporate new burnup and enrichment curves
- Display information with the polynomial explicitly stated
- Include diagrams of approved arrays 5
TS Changes
- Currently 2150 ppm
- May increase in response to accident conditions analysis 6
TS Changes
- Incorporate new arrays
- Update boron concentration
- Reduce radially averaged enrichment from 4.8 wt% to 4.65 wt%
7
New TS
- 5.5.21 - Spent Fuel Storage Rack Neutron Absorber Monitoring program
- Will consider upcoming NRC Generic Letter Monitoring of Neutron-Absorbing Monitoring Neutron Absorbing Materials in Spent Fuel Pools
- Recent Dresden OE
- License extension
- Plant decommissioning 8
Implementation
- Prior to NGF implementation in each unit
- C Considering id i a li license condition diti ffor a specified period of time to transition between TS 9
Methodology
- ISG ISG-2010-01, 2010 01 Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools
- NEI 12-16, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants Plants, Revision 1
- EPRI Depletion Benchmark Reports
- Multiple p NUREGs 10
Recent Licensing Actions
- Comanche Peak
- Prairie Island
- Turkey Point
- Insert material similar to:
- LaSalle
- Peach P h Bottom B tt
- Quad Cities
- Criticality code usage similar to:
- Millstone 2 11
ISG Item 1 - Fuel Assembly Selection
- Palo Verde will demonstrate that variations in design are adequately accounted for in a single, limiting, fuel assembly design
- CE St Standard d dF Fuell
- CE Value Added Pellet
- Westinghouse NGF (8 LUAs)
- AREVA Advanced CE CE-16 16 HTP (8 LTAs) 12
ISG Item 2 - Depletion Analysis
- Depletion parameters will impact the isotopic inventory of burned fuel
- Fuel type
- Axial burnup
- Moderator temperature
- Reactor power
- Soluble boron
- Burnable absorbers 13
ISG Item 2.a - Depletion Uncertainty
- The EPRI methodology will be used to demonstrate the 5% depletion uncertainty is conservative for Palo Verde
- Fission product uncertainty explicitly considered 14
ISG Item 2.b - Reactor Parameters
- Limiting axial moderator temperature profiles derived past, past present, present and anticipated profiles
- Same methodology gy employed p y at Comanche Peak
- Analysis performed at 4070 MWth
- Licensee controls include verification of radial power distribution di ib i anddT T-cold ld 15
ISG Item 2.c - Burnable Absorbers
- Palo Verde has used the following integral burnable absorbers
- B4C rods in CE STD Fuel
- Erbia in CE STD Fuel and Value Added Pellet
- Integral Fuel Burnable Absorber (IFBA) in NGF
- Gadolinia in AREVA Fuel
- Analysis will not credit Erbia, Erbia B4C, C or Gadolinia
- NGF fuel modeled with IFBA in all 236 pins for depletion p analysis y onlyy
- Pool model assumes no burnable absorbers 16
ISG Item 2.d - Rodded Operation
- Guide tube wear program
- End of cycle check will ensure that fuel assemblies experienced an insignificant amount of rodded operation at hot full p
power 17
ISG Item 3 - Criticality Analysis
- SCALE 6.1.2 will be used in the analysis
- KENO V.a solves the eigenvalue (keff ) problem in 3D using the Monte Carlo method
- 238 Group ENDF/B-VII will be used as the library
- Millstone LAR used SCALE 6.0 with the KENO V.a module and 238 Group ENDF/B-VII library 18
ISG Item 3.a - Axial Burnup Profile
- Bounding axial burnup profiles selected from past, past present, present and anticipated profiles
-CCycle l specific ifi li licensee controls t l iinclude l d checks h k on cutback regions (blanket), fuel design, and moderator temperature
- Same methodology used at Comanche Peak and Prairie Island 19
ISG Item 3.b - Rack Model
- Dimensions and tolerance of racks are traceable to design documents
- Borated aluminum insert B-10 B 10 areal density conservatively modeled at quantity less than minimum certified areal density 20
ISG Item 3.c - Interfaces
- All interfaces are evaluated and all interfaces are an acceptable 2x2 array
- Palo Verde has only one rack design
- No gaps modeled between rack modules 21
ISG Item 3.d - Normal Conditions
- Analysis demonstrates that keff 0.95 at less than the TS required boron concentration for:
- Fuel movement
- Fuel inspection and reconstitution
- Foreign Object Search and Retrieval
- Limiting normal condition to initiate accident identified 22
ISG Item 3.e - Accident Conditions
- Analysis demonstrates that keff 0.95 at less than the TS required boron concentration for
- Misloaded or dropped single fresh fuel assembly into, outside of, or on top of spent fuel racks
- Multiple misloaded fuel assemblies
- Loss of SFP cooling
- Seismic events 23
ISG Item 3.e (contd.)
- Limiting dilution event reduces pool boron from 2150 ppm to 1900 ppm
- TRM requires boron concentration to be maintained at 4000 ppm 24
ISG Item 4 - Code Validation
- Will perform criticality code validation in accordance with NUREG/CR-6698
- Data carefully considered to identify trends consistent with NUREG-1475 NUREG 1475
- HTC experiments will be included
- Fission products will be explicitly accounted for
- No lumped fission products will be used 25
Palo Verde Arrays
- 6 arrays will be analyzed
- Palo Verde expects to submit between 3 and 6 of the following arrays for approval
- Fi Finall d designs i specify if llocation ti and d orientation of borated aluminum inserts 26
Palo Verde Arrays
- Infinite array of 2 fresh fuel assemblies (Fr) with two blocked locations and no inserts Fr Fr 27
Palo Verde Arrays
- Infinite array of 2 fresh fuel assemblies (Fr) with two trash cans (TC) and two inserts Fr TC TC Fr 28
Palo Verde Arrays
- Infinite array of 3 low reactivity fuel assemblies (Lo) and 1 high (Hi) reactivity fuel assembly with 2 inserts Lo Lo Hi Lo 29
Palo Verde Arrays
- Infinite array of 2 high reactivity fuel assemblies (Hi) and one low reactivity fuel assembly (Lo) with one blocked cell and one insert Hi Lo Hi 30
Palo Verde Arrays
- Infinite array of 4 low reactivity fuel assemblies (Lo) with one insert L
Lo L Lo Lo Lo 31
Palo Verde Arrays
- Infinite array of 4 depleted fuel assemblies (De) with no inserts De De De De 32
Margin Maintenance
- Palo Verde will monitor the margin identified in the analysis
- Cycle specific checks of key input parameters
- 0.005 k additional margin reserved by Palo Verde
- Burnup and enrichment curves will be for keff = 0.99 33
Conclusion
- Palo Verde is proposing an acceptable methodology gy for performing p g SFP criticality y
analysis
- Permanently l installed ll d b borated d aluminum l
inserts will be credited in the analysis
- Request NRC approval in 18 - 24 months 34