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Category:Meeting Briefing Package/Handouts
MONTHYEARML24192A2262024-07-11011 July 2024 Mtg to Exchange Technical Information Regarding Farley, Units 1 & 2, Proposed License Amendment Request to Increase TS 3.6.5 Containment Temperature Limit Completion Using Risk-Informed Process for Evaluation (EPID L-2024-LRM-0086) - Slides ML24190A1082024-07-0808 July 2024 NRC Slides-07/11/2024 Mtg to Exchange Technical Information Regarding Joseph M. Farley Nuclear Plant, Units 1 & 2, Proposed License Amendment Request to Increase TS 3.6.5 Containment Temperature Limit Completion Using Risk-Informed Process ML24134A1062024-05-13013 May 2024 2023 Annual Assessment Meeting Presentation Slides ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML23139A2462023-05-19019 May 2023 Annual Assessment Public Meeting Slides (May 23, 2023) ML22080A0192022-03-18018 March 2022 Annual Assessment Meeting Presentation ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21280A0012021-10-31031 October 2021 Pre-Submittal Meeting Presentation from SNC to Discuss a Future LAR Regarding Change TS to Increase Containment Peak Pressure to Address Several NSALs ML21173A0632021-06-24024 June 2021 Pre-Application SNC Presentation Slides - Removal of Encapsulations from Recirculation Suction Valves ML21057A0182021-02-26026 February 2021 Pre-Submittal Meeting Revise Technical Specification 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) (EPID L-2021-LRM-0023) (Slides) ML21036A1172021-02-0505 February 2021 SNC Slides - Pre-Submittal Meeting on February 16, 2021 - Beacon LAR ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20217L4312020-08-13013 August 2020 Edwin I Hatch, Units 1 and 2; and Vogtle Electric Plant, Units 1, 2, 3, and 4 - Meeting Slides a License Amendment Request for the Emergency Plan (EPID Nos L-2020-LLA-0150 and L-2020-LLA-051 ML20101K6582020-04-10010 April 2020 Annual Assessment ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19149A4222019-05-29029 May 2019 Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361 ML19057A4762019-03-0707 March 2019 Presentation Slides Related to Pre-Application Public Meeting Regarding to Technical Specification 3.3.1 and 3.3.2 (L-2019-LRM-0010) ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation NL-18-1412, Presentation Material for the Measurement Uncertainty Recovery and Spent Fuel Pool Criticality Analysis Pre-Submittal Meeting2018-11-0808 November 2018 Presentation Material for the Measurement Uncertainty Recovery and Spent Fuel Pool Criticality Analysis Pre-Submittal Meeting ML18311A1822018-11-0707 November 2018 November 13, 2018, Joseph M. Farley Nuclear Power Plant, Public Meeting Slides Regarding Spent Fuel Pool Criticality Analyses and Measurement Uncertainty Recovery (Mur) Pre-Application Meeting ML18290B0942018-10-16016 October 2018 October 16, 2018, Public Meeting Presentation Slides Related to July 27, 2018, License Amendment Request to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b. ML18234A4712018-08-23023 August 2018 NRC-Pre Submittal Meeting TSTF-51 for Hatch and TSTF-51 and -471 for Farley - August 23, 2018 ML18136A8902018-05-16016 May 2018 May 21, 2018 Slides for Public Teleconference Regarding Changes to Hatch, Farley, and Vogtle TS 5.2.2.g ML18065A0202018-03-12012 March 2018 March 12, 2018, Public Meeting Presentation ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures NL-16-0388, September 22, 2016, Public Meeting Presentation Slides2016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides ML16260A1162016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides ML15106A2042015-04-22022 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Slide Presentation ML14115A4052014-04-25025 April 2014 2013 End of Cycle Farley Public Meeting Summary Memo ML14108A0052014-04-23023 April 2014 April 23, 2014, Public Meeting Presentation Slides, Southern Nuclear Company, SNC Degraded Grid Design Criteria. ML14120A2252014-04-23023 April 2014 April 23, 2014, Category 1 Public Meeting, J.M. Farley Presentation Slides, Residual Heat Removal Autoclosure Interlock Deletion. ML14135A1732014-02-26026 February 2014 May 16, 2014, J.M. Farley Category 1 Meeting Handout, Duration for Completion of the Flood Hazard Re-evaluation. ML13079A1502013-03-20020 March 2013 Summary of Public Meeting with Joseph M. Farley ML13078A2462013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 2 (3/19) ML13078A2552013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 10 ML13078A2542013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 9 ML13078A2532013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 8 ML13078A2522013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 6 ML13078A2512013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 5 (3/19) ML13078A2502013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 4 ML13078A2482013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 3 (3/19) ML13078A2472013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 2 (3/20) ML13078A2452013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 1 (3/19) ML1016705482010-06-0808 June 2010 Farley Nuclear Plant, NRC Screening Criteria Response ML1009805922010-04-0808 April 2010 Summary of Public Meeting to Discuss Nrc'S Reactor Oversight Process and Nrc'S Annual Assessment of Plant Safety Performance for Period of January 1, 2009 - December 31, 2009 - Joseph M. Farley Nuclear Plant ML0909210352009-03-19019 March 2009 Annual Assessment Meeting Presentation ML0814900902008-05-22022 May 2008 List of Attendees - Joseph M. Farley Nuclear Plant, Annual Public Assessment Meeting ML0729806702007-10-24024 October 2007 Meeting Presentation on GEH Chemical Effects Testing Update ML0715902092007-05-31031 May 2007 Enclosure 7 - Definitions: SSE (Safe Shutdown Earthquake) & OBE (Operating Basis Earthquake) 2024-07-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24192A2262024-07-11011 July 2024 Mtg to Exchange Technical Information Regarding Farley, Units 1 & 2, Proposed License Amendment Request to Increase TS 3.6.5 Containment Temperature Limit Completion Using Risk-Informed Process for Evaluation (EPID L-2024-LRM-0086) - Slides ML24190A1082024-07-0808 July 2024 NRC Slides-07/11/2024 Mtg to Exchange Technical Information Regarding Joseph M. Farley Nuclear Plant, Units 1 & 2, Proposed License Amendment Request to Increase TS 3.6.5 Containment Temperature Limit Completion Using Risk-Informed Process ML24134A1062024-05-13013 May 2024 2023 Annual Assessment Meeting Presentation Slides ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML23139A2462023-05-19019 May 2023 Annual Assessment Public Meeting Slides (May 23, 2023) ML22080A0192022-03-18018 March 2022 Annual Assessment Meeting Presentation ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21280A0012021-10-31031 October 2021 Pre-Submittal Meeting Presentation from SNC to Discuss a Future LAR Regarding Change TS to Increase Containment Peak Pressure to Address Several NSALs ML21173A0632021-06-24024 June 2021 Pre-Application SNC Presentation Slides - Removal of Encapsulations from Recirculation Suction Valves ML21083A2872021-03-24024 March 2021 Pre-Submittal Meeting - Quality Assurance Topical Report Revision to Allow Application of Remote Assessment Techniques During Exigent Conditions ML21057A0182021-02-26026 February 2021 Pre-Submittal Meeting Revise Technical Specification 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) (EPID L-2021-LRM-0023) (Slides) ML21036A1172021-02-0505 February 2021 SNC Slides - Pre-Submittal Meeting on February 16, 2021 - Beacon LAR ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20101K6582020-04-10010 April 2020 Annual Assessment ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19149A4222019-05-29029 May 2019 Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361 ML19057A4762019-03-0707 March 2019 Presentation Slides Related to Pre-Application Public Meeting Regarding to Technical Specification 3.3.1 and 3.3.2 (L-2019-LRM-0010) ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation NL-18-1412, Presentation Material for the Measurement Uncertainty Recovery and Spent Fuel Pool Criticality Analysis Pre-Submittal Meeting2018-11-0808 November 2018 Presentation Material for the Measurement Uncertainty Recovery and Spent Fuel Pool Criticality Analysis Pre-Submittal Meeting ML18290B0942018-10-16016 October 2018 October 16, 2018, Public Meeting Presentation Slides Related to July 27, 2018, License Amendment Request to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b. ML18065A0202018-03-12012 March 2018 March 12, 2018, Public Meeting Presentation ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application NL-16-0388, September 22, 2016, Public Meeting Presentation Slides2016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides ML16260A1162016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides ML15106A2042015-04-22022 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Slide Presentation ML14115A4052014-04-25025 April 2014 2013 End of Cycle Farley Public Meeting Summary Memo ML14108A0052014-04-23023 April 2014 April 23, 2014, Public Meeting Presentation Slides, Southern Nuclear Company, SNC Degraded Grid Design Criteria. ML14120A2252014-04-23023 April 2014 April 23, 2014, Category 1 Public Meeting, J.M. Farley Presentation Slides, Residual Heat Removal Autoclosure Interlock Deletion. ML14108A0042014-04-18018 April 2014 April 23, 2014, Category 1 Public Meeting, J.M. Farley Presentation Slides, Residual Heat Removal Autoclosure Interlock Deletion ML13079A1502013-03-20020 March 2013 Summary of Public Meeting with Joseph M. Farley ML13078A2452013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 1 (3/19) ML13078A2462013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 2 (3/19) ML13078A2472013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 2 (3/20) ML13078A2482013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 3 (3/19) ML13078A2502013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 4 ML13078A2512013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 5 (3/19) ML13078A2522013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 6 ML13078A2532013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 8 ML13078A2542013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 9 ML13078A2552013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 10 IR 05000348/20110122011-07-15015 July 2011 Summary of Public Meeting with Joseph M. Farley Nuclear Plant, to Discuss Safety Significance of Preliminary White Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000348-11-012 and 05000364-11-012 ML1016705482010-06-0808 June 2010 Farley Nuclear Plant, NRC Screening Criteria Response ML1009805922010-04-0808 April 2010 Summary of Public Meeting to Discuss Nrc'S Reactor Oversight Process and Nrc'S Annual Assessment of Plant Safety Performance for Period of January 1, 2009 - December 31, 2009 - Joseph M. Farley Nuclear Plant ML0909210352009-03-19019 March 2009 Annual Assessment Meeting Presentation ML0819603642008-07-10010 July 2008 07/102008-Joseph M. Farley Regulatory Performance Meeting, Results of the NRC 95002 Supplemental Inspection ML0814901062008-05-22022 May 2008 Slides - Joseph M. Farley Nuclear Plant, Annual Public Assessment Meeting, ML0729806702007-10-24024 October 2007 Meeting Presentation on GEH Chemical Effects Testing Update ML0732413392007-09-19019 September 2007 Email from D. Decker, NRR to K. Cotton, NRR Et Al. Final Copy Farley Aitnrc Slides.Ppt ML0732413252007-09-18018 September 2007 Email from K. Cotton, NRR to S. Shaeffer, Rii on Final Farley Aitnrc Slides.Ppt 2024-07-08
[Table view] |
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Southern Nuclear / Westinghouse Proposed Test Plan to Demonstrate the Benefit of Zinc Addition to Mitigate PWSCC Mike Stinson August 25, 2005 Aug 25, 2005 1
Purpose To determine if test data from the proposed program can be used to make informed decisions with respect to regulatory requirements.
Aug 25, 2005 2
Agenda
- Test design & expectations
- Feedback & discussion Aug 25, 2005 3
Description of Farley 2
- Three-loop, Westinghouse PWR 910 megawatts
- Renewal license expiration: 2041 Aug 25, 2005 4
Farley 2 Pilot Plant for Zinc Addition
- Laboratory and test reactor experiments indicated reduced general corrosion and PWSCC mitigation benefits of zinc addition
- EPRI sponsored demonstration plant
- Zinc injection began June 12, 1994
- 30 ppb Cycles 10, 12 - 14
- 15 ppb Cycles 15 - 17 (post SG replacement)
Aug 25, 2005 5
Farley 2 Zinc Addition Experience
- Sig. Radiation benefit observed after S/G Replacement Plant EFPY Channel head dose rate (R/hr)
Farley 2 1.3 0.34 Watts Bar 1.15 2.3 Cook 2 1.11 3.0 Indian Point 3 1.07 3.1 No. Anna 1 1.36 5.0 Ringhals 2 1.34 4.0 Ref: EPRI TR-107566 Aug 25, 2005 6
Farley 2 Oxide Films
- Pulled SG tube film characterization Normalized Atomic Percent Normalized Atomic Percent 100%
Zn Fe Fe 80%
60%
Atom%
Zn Zn Cr Cr Fe Fe
% Cr 40% Cr Ni Ni
% 20% Ni Ni
% 0%
0 14 28 42 56 19 33 47 61 75 0 7 14 32 60 88 17 31 45 59 6 6 6 6 6 2 2 2 2 Depth (nm)
Depth (nm)
Cycle 9 Cycle 10 Ref: EPRI TR-106358-V1 Aug 25, 2005 7
Farley 2 Zinc Addition Experience
- Difficult to assess PWSCC benefit.
Alloy 600 / 82 / 182 Inspections 2002 2004 2005 2R15 2R16 2R17 CRDM Volumetric (UT) Volumetric (EC + UT) Replace (EA-03-009) + BMV + BMV RPV nozzles BMV (ISI Program)
RPV BMI BMV BMV (BL 2003-02)
PRZ nozzles Volumetric + surface BMV BMV (top)
(BL 2004-01) (1 nozzle) Volumetric + surface (2 nozzles)
Aug 25, 2005 8
Farley 2 CRDM Penetration Material
- B&W Tubular Products heat M3935
- Less than optimum annealing heat treat
- Heat M3935 used in penetrations of five RPV heads:
Heat M3935 Industry Experience Plant name # of % # # required % of nozzles in industry inspected repair M3935 in heat heat no. by UT RV head no. M3935 with defect M3935 Oconee 3 68 49% 68 14 20%
Davis-Besse 5 4% 5 3 60%
ANO 1 1 <1% 1 1 100%
Beaver Valley 1 4 3% 4 4 100%
Farley 2 61 44% 61 0 0%
Total 139 139 22
% 100% 16%
Aug 25, 2005 10
Heat M3935 - Industry Locations that reqd repair 65 60 66 53 41 42 54 33 24 48 Orange 47 34 Oconee 3 (Spr 2001) 52 27 17 18 28 55 Orange striped 64 32 11 8 12 35 67 Oconee 3 (Fall 2001) 40 16 3 4 19 43 Red 59 23 7 1 9 25 61 Davis-Besse (Spr 2002) 39 15 2 5 20 44 Green 63 31 10 6 13 36 68 AN0 1 (Fall 2002) 51 26 14 21 29 56 Blue 46 30 22 37 49 Beaver Valley 1 (Spr 2003) 50 36 45 57 62 58 69 Aug 25, 2005 11
Heat M3935 Farley Unit 2 Locations 65 60 66 53 41 42 54 47 33 24 34 48 52 27 17 18 28 55
- M3935 64 32 11 8 12 35 67 locations 40 16 3 4 19 43 59 23 7 1 9 25 61
-Proposed 39 15 2 5 20 44 sample 63 31 10 6 13 36 68 locations 51 26 14 24 29 56 46 30 22 37 49 50 36 45 57 62 58 69 Aug 25, 2005 12
Whats different?
- Farley 2 is the only RPV head with heat M3935 that has not experienced cracking
- Farley 2 is the only plant that operated with heat M3935 and significant zinc chemistry
- Beaver Valley 1 started to add zinc in 2002 and noted SCC in M3935 in Spring 2003 (~20 ppb-mo.)
How can we determine what makes Farley 2 RPV head different?
Aug 25, 2005 13
Mock-up of Sample Removal Aug 25, 2005 14
Test Program Goal
- Demonstrate that zinc addition makes the surfaces of Alloy 600 more resistant to PWSCC.
- Quantify the improvement in life provided by zinc additions.
Aug 25, 2005 15
What is significant about the Farley 2 Alloy 600?
- Exposed to zinc in the primary coolant since 1994
- Integrated zinc exposure 1600 ppb-months at last inspection
- Integrated zinc exposure 1900 ppb-months at RV head replacement
- High susceptibility heat allows comparison testing to show the beneficial effects of zinc Aug 25, 2005 16
Farley U2R17 RV Head Replacement
- Plan to collect two penetration samples
- penetrations # 14 and # 16
~4.3
~2.8 Aug 25, 2005 17
Proposed Program Objectives
- Harvest Alloy 600 Heat M3935 material from the Farley 2 reactor vessel head.
- Characterize surface chemistry
- Assess crack initiation by performing lab tests of segments containing the Zn conditioned material
- Compare samples with and without zinc in film
- Demonstrate benefits of Zn additions Aug 25, 2005 18
Characterize the incorporation of -zinc
- Can compare depth of zinc infiltration in films
- With Cycle 9 exam (pre-zinc)
- With Cycle 10 exam, (310 ppb-months exposure)
- What is the current surface zinc concentration
- How deep has the zinc diffused into the oxide film
- What are the film characteristics
- Can provide limited material to other organizations Aug 25, 2005 19
Prove benefit regarding crack initiation Basic idea
- Fabricate test specimens keeping as-is surface films intact
- Divide specimens into two groups
- Carefully remove zinc from the surface films of one group
- Perform comparison testing Aug 25, 2005 20
Harvest two Heat M3935 penetrations Aug 25, 2005 21
Anticipated Geometry OD specimen ID specimen Strips would be removed from the ID and OD surface of the Farley 2 material
- Assume red surfaces have zinc removed Aug 25, 2005 - Assume green surfaces tested with zinc 22
Basic Approach o machine specimens With Zinc Without Zinc
- Cold work (increase process w/o affecting stress) oxide film (e.g. LOMI)
- Cold work (increase typical concentrations stress) of zinc in the water
- Continue to test without zinc in the simulated primary Aug 25, 2005 water 23
Typical method for testing crack initiation behavior
- Westinghouse has used this configuration to test service & lab Alloy 600/182 Aug 25, 2005 24
Sample size comparison Size (L=3.7) of Bent beam previously used.
stimate specimens om Farley 2 would e ~1.5 long.
Aug 25, 2005 25
Anticipated specimen configuration Subsized specimen Westinghouse will shrink the test fixtures to test subsized specimens.
Aug 25, 2005 26
Key Challenges Constraints Risks
- Material that can be practically
- Special subsized specimens extracted from head penetrations is limited - and test fixtures need to be requires subsized specimens designed and demonstrated
- The material surfaces will have
- Subsized specimens may be significant radioactivity, >3R/hr difficult to handle (cannot be decontaminated)
- May be difficult to compare
- Testing is costly and time subsized sample data with consuming large sample data Aug 25, 2005 27
Heat M3935 Service Experience 90%
80%
70%
60%
50%
Estimated Time to 10% Initiation Log. (Estimated Time to 10% Initiation) 40%
30%
20%
Farley 2 started to add zinc at 10% ~9.6 EDY 0%
1.0 10.0 100.0 EDY at 600 deg F Aug 25, 2005 28
rojected Performance at levated Temperature 0%
680F 600F Need to accelerate cracking to demonstrate 0%
zinc effectiveness 0%
0%
Estimated Time at 600F to 50% Initiation Estimated Time at 653F to 50% Initiation 0%
Estimated Time at 662F to 50% Initiation 0% Estimated Time at 680F to 50% Initiation Log. (Estimated Time at 600F to 50%
Initiation) 0%
0%
0%
0%
0.1 1.0 10.0 100.0 High test temperatures Effective Years will accelerate cracking Aug 25, 2005 29
Anticipated Performance at Elevated Temp & Stress Crack Initiation Tests (no Zinc) in 680F lab primary water Assumed 1st failure of 140% Farley specimen with zinc surface Zinc improvement factor 130%
120%
% Service Stress 110%
100%
90%
80%
0.1 1.0 10.0 Time at Temperature (years) 100% service stress 110% service stress 120% service stress 140% service stress estimate with Zn surface Aug 25, 2005 30
Proposed Program -
Tasks & Schedule Project Timeline - Crack Initiation Receive and characterize Farley material Complete Farley 2 Initiate Farley 2 Specimen Testing Specimen Testing 0 3 6 9 12 15 18 21 24 27 30 mo.
Initiate Baseline Complete Specimen Testing Baseline Specimen Comparison Test Specimen Development & Testing of Data Experimental Facility Analysis of Relocation Effect Aug 25, 2005 31
Expected Results &
Implications
- Zinc exposed surfaces of Heat M3935 will show reduced crack initiation compared to similar surfaces with the zinc removed
- Extended crack initiation duration relaxes the need for frequent inspections Aug 25, 2005 32
Benefits
- CRDM Order EA-03-009
- Replacement RV heads Alloy 690
- RPV nozzles ASME XI - ISI Program
- RPV BMI Bulletin 2003-02
- PRZ nozzles Bulletin 2004-01
- MRP Inspection Guidelines (e.g., MRP-139)
Aug 25, 2005 33
Feedback Aug 25, 2005 34