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| | issue date = 02/02/2017 | | | issue date = 02/02/2017 |
| | title = NEI-EPRI Slides. DG-1327 NRC Meeting | | | title = NEI-EPRI Slides. DG-1327 NRC Meeting |
| | author name = Eichenberg T W | | | author name = Eichenberg T |
| | author affiliation = Nuclear Energy Institute (NEI) | | | author affiliation = Nuclear Energy Institute (NEI) |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:DG-1327 ClarificationReactivity Initiated Accident GuidanceT. W. EichenbergEPRI Fuel Reliability Program, Reg | | {{#Wiki_filter:DG-1327 Clarification Reactivity Initiated Accident Guidance T. W. Eichenberg EPRI Fuel Reliability Program, Reg-TAC Chair Sr. Specialist Reactor Safety Analysis, TVA January 25, 2017 |
| -TAC ChairSr. Specialist Reactor Safety Analysis, TVAJanuary 25, 2017 *White Flint, Rockville MD 1 | | * White Flint, Rockville MD 1 |
| Overview*Categories for Discussion | | |
| -Methods & Assumptions | | Overview |
| -Failure Thresholds | | * Categories for Discussion |
| -Release Fractions | | - Methods & Assumptions |
| -Miscellaneous 2 | | - Failure Thresholds |
| PWR vsBWRPerspectiv e*While Rod Eject / Blade Drop are Reactivity Initiated Accidents- | | - Release Fractions |
| -These different events don't share an identical topology | | - Miscellaneous 2 |
| *Analytical space is different | | |
| -Every assumption isn't automatically meaningful to both PWR's and BWR's-Example from item 2.2.5 | | PWR vs BWR Perspective |
| *(a) is PWR speak | | * While Rod Eject / Blade Drop are Reactivity Initiated Accidents |
| *(b) is BWR speak-Example item 2.2.10 | | - These different events dont share an identical topology |
| *Muddy regarding BWR 3 | | * Analytical space is different |
| | - Every assumption isnt automatically meaningful to both PWRs and BWRs |
| | - Example from item 2.2.5 |
| | * (a) is PWR speak |
| | * (b) is BWR speak |
| | - Example item 2.2.10 |
| | * Muddy regarding BWR 3 |
| | |
| | Methods & Assumptions |
| | * Approved Models |
| | - What does account for calculational uncertainties mean? |
| | - Realistic / Risk Informed methods to be allowed? |
| | - Expecting a full RG 1.203 process? |
| | 4 |
| | |
| | Methods & Assumptions |
| | * 5% power DNB/CPR threshold? |
| | - Value is below TS monitoring power level. |
| | * Correlation range of applicability may not extend that low |
| | - DNB/CPR may not be appropriate metric relative to very fast transient condition 5 |
| | |
| | Methods & Assumptions |
| | * Misc. Assumptions |
| | - Are sensitivity studies going to be plant and cycle specific? |
| | - What is NOT a major reactivity feedback? |
| | * Direct Moderator Heating Non-Eq. T-H |
| | - What is meant by manufacturing tolerances? |
| | * Plant , fuel type, and/or cycle specific. |
| | As-built vs bounding tolerance |
| | - Accounting for something vs. |
| | sensitivity/parametric evaluation. |
| | 6 |
| | |
| Methods & Assumptions | | Methods & Assumptions |
| *Approved Models | | * Misc. Assumptions |
| -What does "account for calculational uncertainties mean"? | | - What is meant by wider operating conditions? |
| -Realistic / Risk Informed methods to be allowed?-Expecting a full RG 1.203 process? | | - Effectively, youre saying the determination of limiting conditions is non-linear. |
| 4 Methods & Assumptions
| | * When does the search stop? To survey a larger population implies a realistic assessment. |
| *5% power DNB/CPR threshold? | | - What is sufficient parametric study? |
| -Value is below TS monitoring power level. | | 7 |
| *Correlation range of applicability may not extend that low
| | |
| -DNB/CPR may not be appropriate metric relative to very fast transient condition 5
| |
| Methods & Assumptions | | Methods & Assumptions |
| *Misc. Assumptions | | * Misc. Assumptions |
| -Are "sensitivity" studies going to be plant and cycle specific?
| | - Why do advanced methods need to implement artificial conservatism to compare against failure criteria? |
| -What is NOT a "major reactivity feedback?"
| | - Extensive focus on bounding assumptions |
| *Direct Moderator HeatingNon-Eq. T-H-What is meant by "manufacturing tolerances?"
| | * Seems incompatible with implications of 2.2.4 (limiting scenario tied to non-linear effects, not artificial conservatisms) 8 |
| *Plant , fuel type, and/or cycle specific.As-built vs bounding tolerance
| | |
| -Accounting for something vs. sensitivity/parametric evaluation.
| | Methods & Assumptions |
| 6 Methods & Assumptions
| | * Misc. Assumptions |
| *Misc. Assumptions
| | - Approved hydrogen pickup model is explicit |
| -What is meant by "wider operating conditions"?
| | - Need for an approved hydride orientation model is not as obvious. Need to validate the failure curve utilized. |
| -Effectively, you're saying the determination of limiting conditions is non
| | - Is the use of RG 1.224 account for hydride orientation issue? |
| -linear.*When does the search stop? To "survey a larger population" implies a realistic assessment.
| | 9 |
| -What is "sufficient parametric study"?
| | |
| 7 Methods & Assumptions
| | Failure Thresholds |
| *Misc. Assumptions
| | * EPRI Test Program |
| -Why do advanced methods need to implement artificial conservatism to compare against failure criteria? | | - Why Revision 1 |
| -Extensive focus on bounding assumptions | | * MBT Data / NSRR corrections |
| *Seems incompatible with implications of 2.2.4 (limiting scenario tied to non | | - Temperature Effects |
| -linear effects, not artificial conservatisms) 8 Methods & Assumptions | | - Pulse Effects |
| *Misc. Assumptions | | - Power History Effects |
| -Approved hydrogen pickup model is explicit | | - Hydrogen > 300ppm |
| -Need for an approved hydride orientation model is not as obvious. Need to validate the failure curve utilized.-Is the use of RG 1.224 account for hydride orientation issue? | | - Elongation |
| 9 Failure Thresholds | | - Failure Limits http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000003002005540 10 |
| *EPRI Test Program | | |
| -Why Revision 1 | | Failure Thresholds |
| *MBT Data / NSRR corrections | | * Best Estimate? |
| -Temperature Effects | | - Yes, in the sense that curve fits are relative to nominal data. |
| -Pulse Effects | | - No, in the sense that the shape of curve fits displays negative impact in areas without failures |
| -Power History Effects | | * Low Hydrogen region |
| -Hydrogen > 300ppm | | - No, in the sense that correlation coefficients are in some cases substantially less than 1 11 |
| -Elongation | | |
| -FailureLimit s 10http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000003002005540 Failure Thresholds | | Release Fractions |
| *Best Estimate? | | * Appropriate Location |
| -Yes, in the sense that curve fits are relative to nominal data. | | - Keep information in one place; remove from DG-1327 |
| -No, in the sense that the shape of curve fits displays negative impact in areas without failures*Low Hydrogen region | | - Locate to 1.183, 1.195, etc. (sign of a bigger problem) |
| -No, in the sense that correlation coefficients are in some casessubstantiallylessthan 1 11 Release Fractions | | * Example: Changing dose method constitutes an AST/TID backfit? |
| *Appropriate Location | | 12 |
| -Keep information in one place; remove from DG | | |
| -1327-Locate to 1.183, 1.195, etc. (sign of a bigger problem)*Example: Changing dose method constitutes an AST/TID backfit? | | Release Fractions |
| 12 Release Fractions | | * Transient Fission Gas Release |
| *Transient Fission Gas Release-Database doesn't represent low burnup 13 Miscellaneous | | - Database doesnt represent low burnup 13 |
| *Logistical Issue | | |
| -Approved Analytical Methods must Exist | | Miscellaneous |
| *Method reviews in a timely manner? | | * Logistical Issue |
| *Potential New Method Elements | | - Approved Analytical Methods must Exist |
| -Transient Fission Gas Release / Mechanical aspect | | * Method reviews in a timely manner? |
| -Corrosion/Hydrogen Uptake/Crud | | * Potential New Method Elements |
| -Hydride Characterization | | - Transient Fission Gas Release / Mechanical aspect |
| -FCI Impact if Centerline Melt Allowed | | - Corrosion/Hydrogen Uptake/Crud |
| -Contribution of Fission Gas Release to Pressure Surge 14 Questions?? / Discussion 15}} | | - Hydride Characterization |
| | - FCI Impact if Centerline Melt Allowed |
| | - Contribution of Fission Gas Release to Pressure Surge 14 |
| | |
| | Questions?? / Discussion 15}} |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - NEI Slides ML24229A0012024-08-19019 August 2024 NEI - Spent Fuel Management: Safety and Efficiency Improvements Through Technology and Performance Margins - NRC PIRTs Public Meeting Rev. 8.15.2024 Final ML24218A1832024-07-30030 July 2024 NEI 7-30-24 Trial Use RG 1.247 Path Forward Final ML24172A1952024-06-27027 June 2024 NEI Slides for 06-27-2024 Public Meeting Structures as IROFS at Fuel Cycle Facilities ML24178A0372024-06-26026 June 2024 NRC Power Uprate Review Preparation June 26, 2024 Public Meeting Slides ML24164A1972024-06-17017 June 2024 Public Meeting Slides - NRC Staff Comments and Observations on NEI 10-01, Rev 2 Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit ML24129A1382024-05-0808 May 2024 NEI Slides on Centralized Inspections for May 9, 2024 Public Workshop ML24103A1532024-04-12012 April 2024 NEI Supplemental Information on NRC Comments of NEI 20-07 Rev E (Non-Proprietary) - Slides ML24088A2252024-03-26026 March 2024 NEI Slides for Centralized Inspections March 2024 ROP Public Meeting ML24075A2092024-03-14014 March 2024 NEI Advanced Reactor Di&C Task Force Slides - Accident Monitoring Instrumentation ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24067A0062024-03-0808 March 2024 1 - NRC - Workshop3 - Non-LOCA Release Fractions Feedback - Final ML24067A0072024-03-0808 March 2024 2 - NRC - Workshop3 - Non-LOCA - FFRD - Final ML24067A0092024-03-0808 March 2024 3 - NRC - Worshop3 - CR Dose Presentation - Final ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24043A1162024-02-13013 February 2024 3- EQ Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23115A0302023-04-27027 April 2023 NEI Perspective on Performance Monitoring in Use of Probabilistic Fracture Mechanics for Optimizing Inspections of Non-RPV Pressure Vessels, April 27, 2023 ML23088A0822023-03-30030 March 2023 NEI Presentation - March 30, 2023 PRA Configuration Control Public Meeting ML23082A0572023-03-28028 March 2023 Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk ML23079A2642023-03-23023 March 2023 General Visual Examination of Containment Surfaces Covered by Insulation - March 23, 2023 Public Meeting Slides from NEI ML23210A0042023-03-15015 March 2023 Destination: Termination, NRC Regulatory Information Conference ML23045A2892023-03-14014 March 2023 RIC 2023 - 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric).Operational and Safety Benefits of Risk Informed Applications ML23061A0292023-03-0202 March 2023 NEI Presentation - Advanced Reactor Digital I&C Licensing Workshop 1 ML23013A0782023-01-13013 January 2023 PI&R Inspection Discussion for January 2023 ROP Public Meeting ML23041A4342022-12-15015 December 2022 NEI Presentation for December 15, 2022 Industry Spent Fuel Activities Prioritization Meeting ML22291A4442022-10-11011 October 2022 NEI 22-01 License Termination Plan Process Presentation at October 11 2022 Meeting on NUREG-1757 Vol. 2 ML22266A2632022-09-28028 September 2022 Session 2 - Advanced Reactor Developers Perspectives on Codes and Standards ML22250A7122022-09-21021 September 2022 NEI 22-03 Presentation Slides for NRC Public Meeting (Sept. 21, 2022) 2024-08-20
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24228A2102024-08-20020 August 2024 2024 NEI Early Warning System (EWS) Presentation - NEI Slides ML24229A0012024-08-19019 August 2024 NEI - Spent Fuel Management: Safety and Efficiency Improvements Through Technology and Performance Margins - NRC PIRTs Public Meeting Rev. 8.15.2024 Final ML24218A1832024-07-30030 July 2024 NEI 7-30-24 Trial Use RG 1.247 Path Forward Final ML24197A0652024-07-17017 July 2024 SDP Realism Public Meeting NEI Presentation ML24172A1952024-06-27027 June 2024 NEI Slides for 06-27-2024 Public Meeting Structures as IROFS at Fuel Cycle Facilities ML24178A0372024-06-26026 June 2024 NRC Power Uprate Review Preparation June 26, 2024 Public Meeting Slides ML24164A1972024-06-17017 June 2024 Public Meeting Slides - NRC Staff Comments and Observations on NEI 10-01, Rev 2 Industry Guideline for Developing a Plant Parameter Envelope in Support of an Early Site Permit ML24130A1972024-05-0909 May 2024 NEI Presentation Slides on Rapid and Large-Scale Nuclear Reactor Deployments for Remote Industrial Applications - May 14 2024 Public Meeting ML24129A1382024-05-0808 May 2024 NEI Slides on Centralized Inspections for May 9, 2024 Public Workshop ML24114A1142024-04-18018 April 2024 NEI Supplemental Information on NRC Comments on NEI 20-07, Draft Revision E - April 18 Meeting (Non-Proprietary) ML24103A1532024-04-12012 April 2024 NEI Supplemental Information on NRC Comments of NEI 20-07 Rev E (Non-Proprietary) - Slides ML24092A3132024-04-0303 April 2024 Public Mtg_2024-04-03 Pre-submittal Meeting with the Nuclear Energy Institute (NEI) to Discuss an Update to NEI 03-12, Security Plan Template (Revision 8)_NEI Slides ML24088A2252024-03-26026 March 2024 NEI Slides for Centralized Inspections March 2024 ROP Public Meeting ML24075A2092024-03-14014 March 2024 NEI Advanced Reactor Di&C Task Force Slides - Accident Monitoring Instrumentation ML24075A2102024-03-14014 March 2024 NEI Alan Campbell Slides - Non-Safety-Related with Special Treatment – Digital Considerations ML24082A1792024-03-14014 March 2024 RIC-2024 TH18 True Slides ML24086A5342024-03-14014 March 2024 RIC 2024 TH23 Slides - the Industry’S Innovation Imperative ML24067A2592024-03-13013 March 2024 RIC-2024 W14 Slides - NEI-BHoltzman an Industry Perspective on Advanced Reactor Construction Oversight ML24067A0062024-03-0808 March 2024 1 - NRC - Workshop3 - Non-LOCA Release Fractions Feedback - Final ML24067A0072024-03-0808 March 2024 2 - NRC - Workshop3 - Non-LOCA - FFRD - Final ML24067A0092024-03-0808 March 2024 3 - NRC - Worshop3 - CR Dose Presentation - Final ML24067A0102024-03-0808 March 2024 4 - NRC - Workshop3 - EQ Presentation - Final ML24067A0122024-03-0808 March 2024 6 - NRC - Workshop3 - Best Estimate Dose ML24067A0132024-03-0808 March 2024 7 - NRC - Workshop3 - Closing Remarks ML24067A2882024-03-0808 March 2024 1 (Revised)-NRC_Workshop3_Non-LOCA Release Fraction Feedback-Final ML24043A1162024-02-13013 February 2024 3- EQ Presentation Workshop 2 ML24043A1192024-02-13013 February 2024 1- Impacts on RG 1.183 for Workshop2 ML24043A1202024-02-13013 February 2024 2- CR Dose Presentation Workshop 2 ML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24010A0202024-01-11011 January 2024 Public Meeting on SLR Efficiencies - NEI Presentation ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23261C3792023-09-27027 September 2023 NEI 22-04 Pre-Submittal Meeting with NRC - September 27, 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23242A1662023-08-30030 August 2023 the Future of Nuclear Power: 2023 Baseline Survey (Slides) ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23228A0042023-08-18018 August 2023 NEI Slides for Public Meeting to Discuss Possible Efficiencies on the Subsequent License Renewal Review - August 18, 2023 ML23191A0162023-07-11011 July 2023 NEI Comments on Risk-Informed Process for Evaluation (RIPE) DORL TSG - 7/11/23 Public Meeting Slides from NEI ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23117A3712023-05-0202 May 2023 NEI Lessons Learned Meeting Slides, May 2, 2023 2024-08-20
[Table view] |
Text
DG-1327 Clarification Reactivity Initiated Accident Guidance T. W. Eichenberg EPRI Fuel Reliability Program, Reg-TAC Chair Sr. Specialist Reactor Safety Analysis, TVA January 25, 2017
- White Flint, Rockville MD 1
Overview
- Categories for Discussion
- Methods & Assumptions
- Failure Thresholds
- Release Fractions
- Miscellaneous 2
PWR vs BWR Perspective
- While Rod Eject / Blade Drop are Reactivity Initiated Accidents
- These different events dont share an identical topology
- Analytical space is different
- Every assumption isnt automatically meaningful to both PWRs and BWRs
- Example from item 2.2.5
- Example item 2.2.10
Methods & Assumptions
- What does account for calculational uncertainties mean?
- Realistic / Risk Informed methods to be allowed?
- Expecting a full RG 1.203 process?
4
Methods & Assumptions
- 5% power DNB/CPR threshold?
- Value is below TS monitoring power level.
- Correlation range of applicability may not extend that low
- DNB/CPR may not be appropriate metric relative to very fast transient condition 5
Methods & Assumptions
- Are sensitivity studies going to be plant and cycle specific?
- What is NOT a major reactivity feedback?
- Direct Moderator Heating Non-Eq. T-H
- What is meant by manufacturing tolerances?
- Plant , fuel type, and/or cycle specific.
As-built vs bounding tolerance
- Accounting for something vs.
sensitivity/parametric evaluation.
6
Methods & Assumptions
- What is meant by wider operating conditions?
- Effectively, youre saying the determination of limiting conditions is non-linear.
- When does the search stop? To survey a larger population implies a realistic assessment.
- What is sufficient parametric study?
7
Methods & Assumptions
- Why do advanced methods need to implement artificial conservatism to compare against failure criteria?
- Extensive focus on bounding assumptions
- Seems incompatible with implications of 2.2.4 (limiting scenario tied to non-linear effects, not artificial conservatisms) 8
Methods & Assumptions
- Approved hydrogen pickup model is explicit
- Need for an approved hydride orientation model is not as obvious. Need to validate the failure curve utilized.
- Is the use of RG 1.224 account for hydride orientation issue?
9
Failure Thresholds
- Why Revision 1
- MBT Data / NSRR corrections
- Temperature Effects
- Pulse Effects
- Power History Effects
- Hydrogen > 300ppm
- Elongation
- Failure Limits http://www.epri.com/abstracts/Pages/ProductAbstract.aspx?ProductId=000000003002005540 10
Failure Thresholds
- Yes, in the sense that curve fits are relative to nominal data.
- No, in the sense that the shape of curve fits displays negative impact in areas without failures
- No, in the sense that correlation coefficients are in some cases substantially less than 1 11
Release Fractions
- Keep information in one place; remove from DG-1327
- Locate to 1.183, 1.195, etc. (sign of a bigger problem)
- Example: Changing dose method constitutes an AST/TID backfit?
12
Release Fractions
- Database doesnt represent low burnup 13
Miscellaneous
- Approved Analytical Methods must Exist
- Method reviews in a timely manner?
- Potential New Method Elements
- Transient Fission Gas Release / Mechanical aspect
- Corrosion/Hydrogen Uptake/Crud
- Hydride Characterization
- FCI Impact if Centerline Melt Allowed
- Contribution of Fission Gas Release to Pressure Surge 14
Questions?? / Discussion 15