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MONTHYEARNL-03-2395, Request for Relaxation of Order EA-03-0092003-12-0303 December 2003 Request for Relaxation of Order EA-03-009 Project stage: Request ML0336504452003-12-31031 December 2003 Meeting Notice with Southern Nuclear Co. and NRC to Discuss Licensee'S Request Dated December 3, 2003, for Relaxation of Order EA-03-009 Project stage: Meeting ML0403000292004-01-29029 January 2004 Meeting Summary with Southern Nuclear Operating Company on Request for Relaxation of Order EA-03-009 Interim Inspection Requirements for Reactor Pressure Vessel Heads (Tac No. MC1519) Project stage: Meeting ML0402903882004-01-29029 January 2004 Meeting Handouts - Enclosure 2 - Joseph M. Farley Plant Reactor Vessel Head Penetration Nozzle Inspection Relaxation Unit 2 Spring 2004- 2R16 Project stage: Meeting ML0407004792004-03-10010 March 2004 Withdrawal of Relaxation Request EA-03-009 Project stage: Withdrawal ML0918705092009-07-17017 July 2009 G20090346/LTR-09-0303/EDATS: SECY-2009-0304 - Ltr. Mario Bonaca Report on the Safety Aspects of the License Renewal Application for the National Bureau of Standards Test Reactor Project stage: Other 2004-01-29
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24260A0792024-09-23023 September 2024 9/23/2024 Pre-Submittal Meeting - Joseph M. Farley Nuclear Plant, Units 1 and 2, LAR to Change UFSAR for Exception to RG 1.183, Revision 0, Table 3 - Footnote 11 (EPID L-2024-LRM-0108) - Meeting Slides ML24192A2262024-07-11011 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 ML24088A1662024-04-0303 April 2024 SNC Slides - Pre-Submittal Meeting on April 3, 2024 - Farley LAR Changing TS 3.6.5 Containment Air Temperature Using RIPE 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 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) 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) 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) 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 2024-09-23
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Joseph M. Farley Nuclear Plant 0 0
Reactor Vessel Head Penetration w Nozzle Inspection Relaxation Unit 2 Spring 2004 -2R16 Mike Stinson Vice President Southern Nuclear 1
Agenda
- 1. Introduction and Purpose
- 2. NRC Order EA-03-009 Overview.
Safety Issues
- Inspection Requirements
- 3. SNC Response to Order
- 4. Specific FNP 2R1 6 Relaxation Request
- 5. Basis for FNP 2R16 Relaxation Request
- 6. FNP 2R16 Spring 2004 Inspection Plans
- 7. Summary
- 8. NRC Feedback 2
- 1. Introduction and Purpose
- Discuss NRC Order requirements
- Discuss Farley's reactor vessel head inspection history and results
- Discuss specific relaxation request for 2R1 6, basis for request, and inspection plans
- Receive NRC feedback on relaxation request 3
- 2. NRC Order EA-03-009
- Corrosion of the RPV head
- Nozzle ejection
- FNP Unit 2 is in the "High" category for susceptibility to PWSCC
- Inspection Requirements - each outage
- RPV head bare metal visual
- Penetration nozzle non-visual NDE 4
- 3. SNC Response to Order
- SNC consented to the Order
- SNC also requested relaxation of the required inspection coverage due to the physical limits imposed by:
- "Footprint" of the CRDM shroud on the head
- Configuration of the nozzle bottoms (OD thread and ID taper)
- NRC approved the requested relaxation
- An Order revision reflecting these generically applicable relaxations is expected soon 5
- 4. Specific U2R16 Relaxation Request
- Farley will perform IV. C.(1)(a), bare metal visual of the RPV head
- Relaxation is requested to not perform non-visual examination per Item IV.C.(1)(b)
- Relaxation is requested per Order Item IV.F.(2) because compliance would result in hardship without a compensating increase in safety
- The hardship entailed is an estimated 4.1 Rem of additional radiation exposure to inspection personnel 6
- 5. Basis for Relaxation Request
- Cracks through either the nozzle or J-groove weld can cause corrosion only after they reach the nozzle annulus area.
- Corrosion products occupy more volume than the steel corroded and therefore are forced to the head surface.
- Bare metal visual inspection will detect corrosion products on the head surface.
7
- 5. Basis for Relaxation Request (continued)
- Fall 2002 2R1 5 bare metal visual inspection of the head and UT exam of the nozzles detected no evidence of cracks.
- Analysis demonstrates that nozzle cracks propagating from below the examined volume (or from flaws within the examined volume too small to detect) would take >2 operating cycles to cause leakage.
- Industry experience shows that leakage over multiple operating cycles is required for head corrosion to threaten a LOCA.
8
- 5. Basis for Relaxation Request (continued)
- Unit 2 head replacement is planned for fall 2005 at 2R17.
- Analysis demonstrates that about 12 cycles of operation are needed for a circumferential crack to threaten nozzle ejection.
- Only 2 cycles will have elapsed since the last nozzle UT in fall 2002 (2R15) when the planned head replacement occurs in fall 2005 (2R1 7)
- 5. Basis for Relaxation Request (continued)
Unit 2 has injected zinc into the RCS for
>5 years; SNC believes this has mitigated initiation of PWSCC (as has been shown by laboratory testing).
- Unit 2 will have accrued fewer EDY at 2R1 6 (16.8 EDY) than Unit 1 had when found crack-free by BMV and UT examination per the Order in spring 2003 at 1R1 8 (17.5 EDY).
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5 Basis for Relaxation Request U
Summary
- Bare metal visual will address the RPV head corrosion safety concern
- corrosion products will appear on the RPV head
- industry experience demonstrates multiple operating cycles are required to threaten a LOCA
- Analysis shows NDE each outage is not needed to address nozzle ejection safety concern
- circumferential cracking requires about 12 cycles to threaten nozzle ejection 11
- 6. Farley Unit 2 Spring 2004 Inspection Plans
- Farley will perform a bare metal visual inspection of the outer surface of the RPV top head per Order Item IV. Ca(1)(a).
- Absent approval of the requested relaxation of the Order, Farley will perform UT examination of the RPV penetration nozzles per option IV.C.(1 )(b)(i).
- Farley will also perform a visual examination of the outer surface of the RPV bottom head. as. described in SNC's response to NRC Bulletin 2003-02. 12
- 7. Summary
- Performing only a bare metal visual inspection provides adequate assurance that the safety concerns of Order EA-03-009 are met.
- This is supported by the previous crack-free inspection history and crack propagation time analyses for FNP Unit 2.
- Performance of non-visual NDE during the spring 2004 Unit 2 outage (2R1 6) would therefore impose a hardship (4.1 Rem dose to inspection personnel) without a compensating increase in the level of quality and safety.
- 8. NRC Feedback
- Projected Decision Date (2R1 6 Outage Starts 3/13/2004) 14
4' Dia. Penotraflon Nozzle Minimum
\ Interference Fit Zone J-Groove Weld I Minimum Cladding O.D. Thread Approx Lower Limit of UT Coverwage I.D. Taper
- .8;; Penetration nozzle volume I'j W covered by UT exam during L. ; fall 2002 outage 2R15 NOT TO SCALE FNP UNIT 2 TYPICAL PENETRATION NOZZLE CROSS-SECTION
NRC Bulletins Issued NRC Order 2002-01 EA-03-009 200 1-01 2002-02 Issued 2R14 1R17 21 U15 lR18 2R16 1R19 2R17 Al I I l I I _-
l 1l 1 - 1S1 1S6 S I-n I _
2001 2002 .2003 2004 2005 2006 Performed Unit 2 Performed Unit 2 Relaxation Planned Unit 2 Best-Effort 100% BMV Requested to RPV Head BMV Head Head Inspection Perform Only Replacement Inspection and 100% BMV Nozzle UT Exam on Unit 2 Performed Unit 1 Performed Unit 1 Planned Unit 1 100% BMV 100% BMV RPV Head Head Inspection Head Inspection Replacement and Nozzle UT & ECT Exams Farley Nuclear Plant Units 1 & 2 RPV Closure Head Inspection and Replacement Timeline