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Category:Meeting Briefing Package/Handouts
MONTHYEARML24302A0912024-10-0505 October 2024 Welcome Slides ML24274A3232024-10-0404 October 2024 S9P6-Kojima Concrete Harvesting Activities Plans and Related Priority Research Topics in Japan R2 ML24257A0902024-09-17017 September 2024 05 Osvaldo Pensado Swri September 2024 NRC Ai Public Workshop 09/17/2024 ML24263A2552024-09-17017 September 2024 02 Doug Eskins NRC September 2024 NRC Ai Public Workshop 09-17-2024 ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0182024-07-23023 July 2024 3-Base: Isolation/Observations - Final Stakeholder Meeting, 07-24-24 ML24172A3022024-06-25025 June 2024 Extremely Low Probability of Rupture (Xlpr) Code, NRC Perspectives and Activities ML24045A2332024-03-12012 March 2024 RIC 2024 W11 - Human in the Loop: the Changing Role of Humans in New Advanced Reactor Designs - D. Desaulniers Presentation ML24005A1022024-01-0505 January 2024 RES - High Burnup Fuel Source Term Accident Analysis Briefing - Workshop Jan 09, 2024 ML23214A0342023-08-0202 August 2023 RIC 2023 Regulatory Information Conference (RIC) Project Advanced Characterization of ATF Cladding for Understanding Their Degradation Under Short-time Temperature Excursions and Implications in Dry Storage ML23200A3442023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Joseph Staudenmeier on Models for Thermal Hydraulic Safety Analysis ML23045A2852023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) Advancing the Infrastructure for Using PRA in Decision-Making Technical Session T5 ML22340A5892022-12-13013 December 2022 Boas HPS_Drop-in_12-13-2022 ML22297A0322022-10-31031 October 2022 Nuclear Data at the Us NRC ML22235A6512022-09-0101 September 2022 FY22-24 NRC Research Prospectus Final for Review ML22220A0762022-08-0808 August 2022 Advanced Reactor Research Activities in Nuclear Innovation ML22221A2422022-07-30030 July 2022 KM Session Ai Strategic Plan Overview 20223006 ML22203A0852022-07-27027 July 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22174A3242022-06-27027 June 2022 NRC Presentation: NRC Harvesting Strategy, Coordination, and Activities ML22178A1792022-06-27027 June 2022 Harvesting - an Overview and Historical Perspective, June 27, 2022 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 NUREG-1829, Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results2022-06-14014 June 2022 Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results ML22166A3492022-06-14014 June 2022 Passive System LOCA Frequency Estimation and Break Size Selection ML22143A9262022-05-26026 May 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22131A3362022-05-13013 May 2022 DG-1402 April 13 2022 Public Meeting Slides ML22136A1102022-05-11011 May 2022 Presentation 1 - NRC Opening Remarks by T. Aird and C. Barr ML22102A0002022-04-0505 April 2022 Us NRC and Research Centre Rez (Czech Rep.) 2nd Bilateral Meeting, 04/05/2022 - NRC Presentation ML22083A0302022-03-24024 March 2022 March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel ML22040A1382022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Franovichm - Safety Improvements Using Risk Insights ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview ML21228A0812021-08-16016 August 2021 Agenda Dtaant Workshop Sept 2021 ML21221A1912021-08-11011 August 2021 Presentation on Regulatory Guide 1.9 Revision 5 for NRC Public Meeting with NEI on August 11 2021 ML21217A2612021-08-0909 August 2021 12A - NRC - Xlpr Slides for Mtls Exchange ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21183A2012021-07-0707 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21183A2022021-07-0606 July 2021 Presentation to Fc Meeting ACRS Scheduled for July 7 2021 ML21113A0822021-05-0606 May 2021 Appendix B - Workshop Slides ML21098A1292021-04-0606 April 2021 1E - Sierra Modeling ML21098A1312021-04-0606 April 2021 1G - Fragility ML21098A1282021-04-0606 April 2021 1D - Modeling Overview ML21098A1262021-04-0606 April 2021 1B - Overview ML21069A0202021-03-0303 March 2021 Phenomena Identification and Ranking Tables: U.S. NRC Perspective ML21057A1672021-03-0101 March 2021 Public Meeting - HELB - NRC Presentations on Alternative Acceptance Criteria for Postulating Pipe Break Locations - March 2021 ML20336A0042020-12-0707 December 2020 Opening Session - NRC Public Workshop on Advanced Manufacturing Technologies for Nuclear Applications ML20304A5012020-11-0505 November 2020 Rev 3 - ACRS Fc Briefing for the Advisory Committee on Reactor Safeguards Full Committee - Final ML20283A6162020-10-15015 October 2020 Presentation: Nrc'S Preparations for Advanced Reactor Licensing, ORNL Molten Salt Workshop, October 14-15, 2020 ML20289A6582020-10-0808 October 2020 Enclosure 3 - NRC Presentation on Nrc'S Crediting FLEX Effort 2024-09-17
[Table view]Some use of "" in your query was not closed by a matching "". Category:Slides and Viewgraphs
MONTHYEARML24302A0912024-10-0505 October 2024 Welcome Slides ML24274A3232024-10-0404 October 2024 S9P6-Kojima Concrete Harvesting Activities Plans and Related Priority Research Topics in Japan R2 ML24263A2552024-09-17017 September 2024 02 Doug Eskins NRC September 2024 NRC Ai Public Workshop 09-17-2024 ML24257A0902024-09-17017 September 2024 05 Osvaldo Pensado Swri September 2024 NRC Ai Public Workshop 09/17/2024 ML24213A0642024-07-31031 July 2024 Presentation - NRC Work on Thermal Aging Embrittlement of Austenitic Stainless Steel Weld Metal Implications for Section XI Flaw Evaluation Procedures ML24205A0182024-07-23023 July 2024 3-Base: Isolation/Observations - Final Stakeholder Meeting, 07-24-24 ML24205A0212024-07-23023 July 2024 1-Insights from 07-18-24 Workshop on Risk Metrics and Reliability Data to Support Risk-Informed Program for Advanced Reactors ML24205A0222024-07-23023 July 2024 Master Slide - Advanced Reactor Stakeholder Public Meeting - 2024-07-24 ML24172A3022024-06-25025 June 2024 Extremely Low Probability of Rupture (Xlpr) Code, NRC Perspectives and Activities ML24029A2372024-03-12012 March 2024 03/12-14/2024 Regulatory Information Conference (RIC) ML24045A2332024-03-12012 March 2024 RIC 2024 W11 - Human in the Loop: the Changing Role of Humans in New Advanced Reactor Designs - D. Desaulniers Presentation ML24005A1022024-01-0505 January 2024 RES - High Burnup Fuel Source Term Accident Analysis Briefing - Workshop Jan 09, 2024 ML23214A0342023-08-0202 August 2023 RIC 2023 Regulatory Information Conference (RIC) Project Advanced Characterization of ATF Cladding for Understanding Their Degradation Under Short-time Temperature Excursions and Implications in Dry Storage ML23200A3442023-06-20020 June 2023 National Organization of Test, Research, and Training Reactors 2023 Annual Conference Presentation by Joseph Staudenmeier on Models for Thermal Hydraulic Safety Analysis ML23166A1122023-06-14014 June 2023 Presentation on Artificial Intelligence and Machine Learning Support for Probabilistic Fracture Mechanics Analysis ML23193B0422023-06-11011 June 2023 Applications of the Extremely Low Probability of Rupture (Xlpr) Code ML23150A0242023-05-17017 May 2023 0a -Welcome (NRC) ML23150A0262023-05-17017 May 2023 0c - Working Group ML23121A2552023-05-0202 May 2023 Public Meeting to Discuss Revision of Regulatory Guide 1.200 and Updates to Technical Guidance Related to Risk-Informed Activities ML23045A2852023-03-14014 March 2023 RIC 2023 03/14/2023 to 03/16/2023 Regulatory Information Conference (RIC) Advancing the Infrastructure for Using PRA in Decision-Making Technical Session T5 ML23058A2132023-02-27027 February 2023 HTGR Workshop 2023 Slides - Final ML22297A0322022-10-31031 October 2022 Nuclear Data at the Us NRC ML22235A6512022-09-0101 September 2022 FY22-24 NRC Research Prospectus Final for Review ML22220A0762022-08-0808 August 2022 Advanced Reactor Research Activities in Nuclear Innovation ML22221A2422022-07-30030 July 2022 KM Session Ai Strategic Plan Overview 20223006 ML22203A0852022-07-27027 July 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22179A3342022-06-28028 June 2022 NRC Public Meeting - Advanced Manufacturing Technologies, June 28, 2022 ML22178A1832022-06-27027 June 2022 NRC Harvesting Strategy, Coordination, and Activities, June 27, 2022 ML22178A1792022-06-27027 June 2022 Harvesting - an Overview and Historical Perspective, June 27, 2022 ML22174A3242022-06-27027 June 2022 NRC Presentation: NRC Harvesting Strategy, Coordination, and Activities ML22166A3492022-06-14014 June 2022 Passive System LOCA Frequency Estimation and Break Size Selection NUREG-1829, Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results2022-06-14014 June 2022 Example Xlpr LOCA Frequency Estimates Compared to NUREG-1829 Expert Elicitation Results ML22143A9262022-05-26026 May 2022 ROP Public Meeting Ai Strategic Plan Presentation ML22131A3362022-05-13013 May 2022 DG-1402 April 13 2022 Public Meeting Slides ML22136A1102022-05-11011 May 2022 Presentation 1 - NRC Opening Remarks by T. Aird and C. Barr ML22102A0002022-04-0505 April 2022 Us NRC and Research Centre Rez (Czech Rep.) 2nd Bilateral Meeting, 04/05/2022 - NRC Presentation ML22083A0302022-03-24024 March 2022 March 2022 Joint EPRI-INL ATF Workshop - NRC Code Development and Assessment for Accident Tolerant Fuel ML22080A0472022-03-22022 March 2022 Anticipated Impacts of Nuclear Accidents, Presentation for 2022 Society for Benefit-Cost Analysis Annual Conference, 3-22-2022 ML22083A2042022-03-15015 March 2022 Presentation on NRC Regulatory Research - Enabling Regulatory Readiness for Accident Tolerant Fuel, March 22, 2022 ML22140A3092022-03-0808 March 2022 bush-goddards-hv-w12 ML22140A3112022-03-0808 March 2022 coffins-hv-t7 ML22040A1382022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Franovichm - Safety Improvements Using Risk Insights ML22040A1802022-03-0808 March 2022 Regulatory Information Conference (RIC) RIC 2022 Technical Session T8 - Thaggard M - Safety Marker Study ML21257A2182021-09-16016 September 2021 AMT Subtask 1A - Lpbf Dgd - Sept 16, 2021 Public Webinar ML21277A1252021-08-18018 August 2021 8 Gonzalez and Humberstone MOU Overview ML21228A0812021-08-16016 August 2021 Agenda Dtaant Workshop Sept 2021 ML21221A1912021-08-11011 August 2021 Presentation on Regulatory Guide 1.9 Revision 5 for NRC Public Meeting with NEI on August 11 2021 ML21217A2612021-08-0909 August 2021 12A - NRC - Xlpr Slides for Mtls Exchange ML21187A1712021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit ML21187A1702021-07-0707 July 2021 Updated Presentation to Fc Meeting ACRS - Final - 7-6-21 Rev Minor Edit 2024-09-17
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Text
Condition of Pyrotrol III, 44-Year Raychem Naturally Aged Flamtrol, and RSCC Cable Firewall III Cable (15 years)
Condition of Rockbestos (Cerro)
Pyrotrol III Outer Jacket.
Once the braid and jacket were removed, the underlying conductor insulation was generally in good shape, intact, and moderately flexible
The Surprise:
Once we recovered the Cerro Pyrotrol III cable, we discovered that instead of the name Cerro they were Rockbestos Pyrotrol III cable.
INDIVIDUAL PYROTROL III CONDUCTOR WITH OUTER JACKET REMOVED.
The Chemically Cross-linked polyethylene conductor insulation was in reasonably good condition after 44 years of installation in an average of 150°F (65.5°C) ambient environment. There were ambient excursions up to about 180°F (82.2°C). These were control conductors with little or no heat rise.
The stranded copper conductors did not exhibit any corrosion or rust.
CONDITION OF PYROTROL III AT THEIR TERMINATION LUGS. The shiny clear substance on and behind the terminal lug is Patel Engineers Conformal Coating (PECC).
RAYCHEM FLAMTROL wire and cable rated 1000 Volt, Single or Multi-Conductor, Cross-Linked Polyethylene (XLPE) insulated and jacketed Control Cable.
The photo at right shows how the outer jacket had split approximately every 1/8 to every 1/4 along the entire length of the cable.
Terminal Box Rust and Corrosion: The photo to the right shows a typical CNS terminal box inside the Steam Tunnel. While not all terminal boxes were rusted and corroded, several were. The pictured terminal box is among the worst case examples (2014).
Rust formation in terminal boxes is not necessarily a failure mechanism. In a static state, the outer jacket will prevent rust from reaching the conductor insulation. The evidence for this is shown that after 42 years in the hot and humid Steam Tunnel, the rust had not reached a point where it would cause any damage to the cables.
THE PROBLEM WITH EXCESSIVE RUST IS IT MAY AFFECT CABLE RATING When cables were being removed, the electrical team used brushes as they pulled the old cable out and the new cable in through the conduit.
They reported that there were significant quantities of rust and corrosion from the conduit walls - along with moisture.
RSCC (Rockbestos)
Firewall III cable was also inadvertently removed during the 2016 outage. It was a small length between two terminal boxes in close proximity to one another in the Steam Tunnel.
The features used for testing the The general cables by AMS were:
results are that Visual and optical microscope inspections all cables Insulation Resistance (IR) removed proved Indenter Modulus to be in good Elongation at Break (EAB) condition, Oxidation Induction Time Thermo-Gravimetric Analysis consistent with Relative Density their aging Scanning Electron Microscopy/Energy Dispersive X-ray levels. Spectroscopy
BALANCE OF CABLES PULLED IN 2018.
More precisely, their Elongation-At-Break and Insulation Resistance would likewise have been about the same as the 2016 cables.
The remaining life of 15-years for the Pyrotrol III cable and 5-years for the Raychem Flamtrol Cable is based on a minimum of 50%
EAB as determined by AMS.
CNS conservatively chose to replace the Pyrotrol III Cables because the remaining life also has to account for any HELB accident.
SAMPLES OF CABLE LENGTHS PASSED OUT FOR YOU TO LOOK CLOSELY The four packages are from the 2018 cable pull. They represent the vintage, manufacturer, and condition.
One yellow cable shows a transition from being in very good condition to being severely degraded within about a foot.
This suggests that the load or nearby equipment was extremely hot at one end.
The conductors, however, are still in good condition and flexible.
RECOMMENDATIONS Know various heat loads affecting cables Get Temp Element data to track ambient Apply as many TEs or Monitors as possible Inspect condition of cable ends periodically Inspect terminal boxes & conduit entry for rust and corrosion Make sure cable qualified life is solidly based (DOR)
Have cables replaced in a conservative time frame