|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19318F9512019-11-20020 November 2019 Presentation Slides for November 20, 2019, Pre-Application Meeting - Request for Revision to Quality Assurance Program Internal Audit Frequency ML19317C9952019-11-12012 November 2019 In-Service Testing Supplemental Position Indication Relief Request NRC Pre-Application Meeting November 18, 2019 ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18190A3922018-06-14014 June 2018 Licensee Presentation Material for June 14, 2018 Public Meeting ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18096A0222018-04-0404 April 2018 Annual Assessment Meeting 04/04/2018 Handouts ML18096A9902018-03-12012 March 2018 NRC Pre-Submittal Call Briefing Notes, Calvert Cliffs Emergency Planning Future Licensing Actions ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML17143A1612017-05-23023 May 2017 Annual Assessment Meeting Handout and Sign in Sheet ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request 2024-05-16
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24310A0672024-11-0505 November 2024 Constellation NRC Pre-Submittal Meeting Slides - Proposed Alternative for Reactor Vessel Closure Stud Exam Optimization ML24137A1882024-05-16016 May 2024 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides ML24100A7672024-04-11011 April 2024 Meeting Slides - Preapplication with Constellation on Planned Fleet Alternative Request to Adopt OMN-2 ML24089A2612024-04-0909 April 2024 Slides - Constellation - Pre-Application Regarding Hooded Masks 4/9/2024 Meeting Slides (L-2024-LLM-0041) ML24029A1742024-01-30030 January 2024 Constellation Pre-Application January 30, 2024, Meeting Slides - Proposed Alternative to Utilize Code Case N-932, Alternative Requirements for Acceptance of Containment Base Metal Corrosion or Erosion ML23317A0712023-11-14014 November 2023 NRC Pre-Submittal Meeting on November 14th, 2023 - TSTF-591 and Selected 50.69 License Condition Updates (EPID L-2023-LLM-0098) (Slides) ML23255A1042023-08-11011 August 2023 Slides - Constellation - Pre-Application EP 9/18/2023 Draft CEG Presubmittal SG Performance Monitoring Plan Meeting Handout ML23157A0352023-06-0606 June 2023 Annual Assessment Meeting for Pa/Md/Ny/Nj Nuclear Power Plants - NRC Presentation Slides NEI 99-01, Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides2023-02-21021 February 2023 Slides - Constellation - Pre-Application EP 2/23/2023 Meeting Slides ML23033A6662023-02-0909 February 2023 Summary of Public Meeting with Constellation Energy Generation, LLC (Constellation) to Discuss Its Request for Alternatives for Certain Steam Generator Weld Inspections for Calvert Cliffs 1 & 2, Byron 1 & 2, Braidwood 1 & 2, and Ginna ML23033A6672023-01-30030 January 2023 Public Call with Constellation January 30, 2023 (Slides) ML22124A1492022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Non-Proprietary (Public) ML22124A1482022-05-10010 May 2022 (Ccnpp) Control Element Assembly (CEA) Recovery Time Improvement Project LAR Pre-Submittal Redacted (Public) ML22013A3942022-01-13013 January 2022 Presentation Information for Pre-Submittal Meeting Regarding Relief Request to Use the Carbon Fiber Reinforced Polymer (Cfrp) Composite System ML21314A4472021-11-10010 November 2021 Slides for Presubmittial Meeting for Proposed Alternative to Adopt ASME Code Case N-921 to Extend the Inservice Inspection Interval ML21165A1942021-06-16016 June 2021 Joint Annual Assessment Meeting for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation ML21165A2882021-06-16016 June 2021 Joint Annual Assessment for Pa/Md/Nj/Ny Nuclear Power Plants - Webinar Presentation (Updated) ML21162A3322021-06-11011 June 2021 BWR Fleet Relief Request Associated with RPV Instrument Nozzle Repairs ML21144A0172021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request Pre-Submittal Meeting ML21134A0162021-05-24024 May 2021 Spent Fuel Pool Cooling - Shutdown Cooling Licensing Design Basis License Amendment Request - NRC Pre-submittal Meeting Telecon May 24, 2021 (EPID L-2021-LRM-0051) (Slides) ML20261G7322020-09-16016 September 2020 Pre-Submittal Slides Extend 120-month Isi/Ist Interval Under 50.55a ML20246G8772020-09-0303 September 2020 Licensee'S Presentation for September 3, 2020 Public Telephone Conference ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20175A8722020-06-23023 June 2020 Risk-Informed Inservice Inspection - U.S Nuclear Regulatory Commission (NRC) - Four Element Risk-Informed Approach ML20163A6542020-06-18018 June 2020 2020 NRC Annual Assessment Webinar Presentation - Pennsylvania and Maryland Facilities (Beaver Valley, Calvert Cliffs, Limerick, Peach Bottom, Susquehanna) ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20168A3192020-06-15015 June 2020 Joint Annual Assessment Meeting for Pa/Md Power Plants - Webinar Presentation ML19246B7162019-08-29029 August 2019 Meeting Between NRC and Exelon Regarding Calvert Cliffs-2 LAR to Use Framatome ATF LTAs ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML18276A0712018-10-0404 October 2018 Exelon'S Presentation for October 4, 2018 Public Pre-Submittal Meeting on Planned Calvert Cliffs 10CFR50.69 LAR ML18171A0842018-06-21021 June 2018 GSI-191 Program Use of Risk Metrics for Containment Sump Tech Spec Operability Determination June 21, 2018 Public Meeting Slides (MF8521, MF8522; L-2016-LRM-0001) ML18136A4932018-05-16016 May 2018 Licensee'S Slides for Pre-Application Meeting W/Exelon Re Planned GSI-191 LAR for Calvert Cliffs (L-2016-LRM-0001) ML18054B3592018-02-27027 February 2018 Slide: NRC Pre-Submittal Meeting for Exelon Fleet LAR to Relocate TS Unit Staff Qualification ANSI Requirements to the QATR, February 27, 2018, Profile Info: Submitted by Frank Mascitelli ML16328A2832016-11-18018 November 2016 Supplemental Presentation Slides for 10/25/2016 Public Meeting Via E-mail from K.Greene to R.Guzman Calvert Cliffs GSI-191 Resolution Update ML16307A4902016-10-25025 October 2016 Presentation Slides from Public Meeting Calvert Cliffs GSI-191 Resolution Update ML16274A0012016-09-30030 September 2016 PWR MSIP Analysis and Measurements ML16242A1782016-09-0101 September 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16198A0012016-07-18018 July 2016 Presentation Slides from Public Meeting Regarding Calvert Cliffs GSI-191 Resolution Update ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML15321A3702015-12-0101 December 2015 GSI-191 Program Strainer Head Loss Testing and Option 2b Closure Approach ML15308A1072015-11-0505 November 2015 TSTF-505 LAR - NRC Pre-Submittal, November 5, 2015 Meeting Slides ML15279A4992015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application ML15282A0832015-10-0808 October 2015 October 8, 2015, Public Meeting Regarding the NFPA-805 License Amendment Application - Final ML15222A5472015-08-31031 August 2015 GSI 191 Program Chemical Effects Testing Update Option 2b Closure Approach ML15152A0822015-06-0404 June 2015 Presentation for the June 4, 2015 Public Meeting Regarding the National Fire Protection Association Standard 805 License Amendment Request ML14230A9132014-08-18018 August 2014 Enclosure - Fuel Performance and Cask Internals - July 17, 2014, Summary of Meeting with Exelon Corporation to Discuss Request for Additional Information No. 4 to the Calvert Cliffs ISFSI License Renewal Application (Docket No. 72-08) TAC L 2024-05-16
[Table view] |
Text
Fuell Performance F P f and Cask Internals Robert E. Einziger, Ph.D.
Meeting to provide Calvert Cliffs Nuclear Power Plant, LLC,, the opportunity pp y to discuss request q for information responses regarding the Calvert Cliffs ISFSI License Renewal with the NRC Staff July 17, 2014 1
Introduction
- Current guidance in NUREG-1927 NUREG 1927 does not address cask/canister internals that are considered important to safety
- Fuel performance for retrievability and cladding integrity functions
- ISG-24 Final Guidance (ML14058B166)
AMP Element 1:
Scope of the Program NUREG-1927: The scope of the program should include the specific structures and components subject to an aging management review
- Components/Materials of Construction
- Specify spent fuel maximum burnup
- Specify S if cladding l ddi ttypes and d maximum i cladding l ddi temperature t t
- Dry y helium e u
- Aging effects for material/environment combinations
- Fuel cladding breach
- A Assemblybl di distortion t ti
- Residual moisture after drying
- Changes in the hydride structure of the cladding 3
AMP Element 2:
Preventive Actions NUREG-1927: Preventive actions should mitigate or prevent the applicable aging effects
- Casks/Canisters dried per the accepted guidance in NUREG -1536, Standard Review Plan for Dry Cask Storage Systems
- Backfilled with helium cover gas
- Maximum cladding temperature is maintained below the recommended ISG-11 Rev 3 limits 4
AMP Element 3:
Parameters Monitored/ Inspected NUREG-1927: Parameters monitored or inspected should be linked to the effects of aging on the intended functions of the particular structure and component
- Surveillance demonstration program meeting ISG-24:
- Maximum cladding temperature
- Inspection for the presence of fission gas in the cover gas
- Inspection for presence of water vapor in the cover gas
- Inspection for hydrogen to determine that any radiolysis of residual or bound water does not produce a flammable condition
- Profilometry at the completion of the storage period to determine creep deformation
- Gas G puncturingt i att completion l ti off storage t to t determine d t i cladding l ddi stress for creep calculations
- Cladding metallography at the completion of storage to determine condition of cladding hydrides h drides 5
AMP Element 4:
Detection of Aging Effects NUREG-1927: Define method or technique, frequency, sample size, data collection, and timing to ensure timely detection of aging effects
- Surveillance demonstration program meeting ISG-24:
- Calibrated thermocouple lances to measure the radial and axial temperature profile
- Fission gas analysis technique for the cover gas with sensitivity to detect release of 1% of the fission gas produced in 1% of the cask rods with the lowest burnup in the demonstration
- Residual moisture detection technique with sensitivity to detect the vapor pressure at the bottom of the demonstration system
- Hydrogen H d d detection t ti ttechnique h i with ith sensitivity iti it to t detect d t t 2%
hydrogen in the cover gas of the demonstration 6
AMP Element 5:
Monitoring & Trending NUREG-1927: Should provide for prediction of the extent of the effects of aging and timely corrective or mitigative actions
- As information/data from a fuel performance surveillance demonstration program becomes available, the licensee will monitor, evaluate, and trend the information via their Operating Experience Program and/or the Corrective Action Program to determine what actions should be taken to manage fuel and cladding performanceperformance, if any
- Similarly, the licensee will use its Operating Experience g
Program and/or Corrective Action Program g to determine what actions should be taken if it receives information/
data from other sources than the demonstration program on fuel performance 7
AMP Element 6:
Acceptance Criteria NUREG-1927: Acceptance criteria, against which the need for corrective action will be evaluated; should ensure that SSC functions are maintained
- ISG-24 acceptance criteria provide detailed guidance
- Cask internals and fuel performance criteria:
- Temperature: spatial distribution and time history accurately determined - necessary since the behavior of the rods in the demonstration to the behavior expected of the rods in storage is temperature dependent dependent.
- Cladding Creep: total creep strain extrapolated to the total approved storage duration based on the best fit to the data, accounting for initial condition uncertainty shall be less than 1% -
ISG-11 temperature limits are based on limiting creep to <1%
8
AMP Element 6:
Acceptance Criteria NUREG-1927: Acceptance criteria, against which the need for corrective action will be evaluated; should ensure that SSC functions are maintained
- Cask internals and fuel performance criteria:
- Hydrogen - maximum hydrogen content of the cover gas over the approved pp storage g p period shall be extrapolated p from the g gas measurements to be less than 5% - limit for precluding possible flammable mixture
- Drying y g - The moisture content in the cask , accounting g for measurement uncertainty, shall indicate no greater than one liter of residual water after the drying process is complete - Drying limit, in terms of residual moisture, in the SRP NUREG-1536
- Fuel rod breach - fission gas analysis shall not indicate more than 1% of the fuel rod cladding breaches. - Recommended maximum number of cladding breaches during normal conditions of storage for containment analysis by ISG-5 9
AMP Element 7:
Corrective Actions NUREG-1927: Corrective actions, including root cause determination and prevention of recurrence, should be timely
- Licensee Corrective Action Program to capture and evaluate surveillance demonstration program data, other information/data, and additional operating experience to i iti t corrective initiate ti and/ord/ preventative t ti actions:
ti
- Corrective actions to prevent reoccurrence
- Extent of condition to other susceptible p components p
- Timely corrective actions 10
AMP Elements 8:
Confirmation Process NUREG-1927: Confirmation process should ensure that preventive actions are adequate & appropriate corrective actions have been completed & are effective
- What follow up action is going to be taken to determine whether preventative or corrective actions are a success
- Method to confirm any actions required are taken 11
AMP Elements 9:
Administrative Controls NUREG-1927: Administrative controls should provide a formal review and approval process
- Training requirements for inspectors or personnel
- Records retention requirements
- Specified p in the Demonstration Project j Plan or alternate surveillance demonstration program meeting the ISG-24 guidance
- Frequency F for f updating d ti AMP based b d on iindustry-wide d t id operational experience 12
AMP Element 10:
Operating Experience NUREG-1927: Include past corrective actions; provide objective evidence to support a determination that the effects of aging will be adequately managed so that the SSC intended functions will be maintained during the period of extended operation
- Surrogate surveillance demonstration programs with storage t conditions diti and d ffuell ttypes similar i il tto ththose iin th the dry storage system that satisfies the ISG-24 acceptance criteria is a viable method to obtain operating p g experience p
- DOE Dry Cask Storage Demonstration Project is viable as a surrogate surveillance program for the industry
- Additional data/research to assess fuel performance 13
References
- ISG The Use of a Demonstration Program as a Surveillance Tool for Confirmation of Integrity for Continued Storage of High Burnup Fuel Beyond 20 Years (ML14058B166) 14
Acronyms
- CFR - Code of Federal Regulations
- DOE - U.S. Department of Energy
- ISG - Interim Staff Guidance
- SRP - Standard Review Plan 15