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| {{#Wiki_filter:}} | | {{#Wiki_filter:~Karen Cot~ton -Re:FiýNnalc6py FarleyTR sl~ espt ae1 Pa e-l'3 From: David Decker To: Karen Cotton; Lauren Quinones; Michael Ernstes; Scott Shaeffer; Stephen Alexander; Tim McGinty Date: 09/19/2007 10:07:22 AM |
| | |
| | ==Subject:== |
| | Re: Final copy Farley AITNRC slides.ppt The updates you suggest look good to me. Thanks. -David>>> Stephen Alexander 09/19/2007 10:00 AM >>>Again, in my view, the short version language will be a bit confusing to laymen. Attached is a suggested version -not longer -not to worry -but simpler language. |
| | It reads as follows: On September 4, 2007 In support of planned maintenance on the 1 B component cooling water (CCW) pump, the licensee needed to start another pump.The Cutler-Hammer breaker for the IC CCW pump failed to close when the licensee attempted to start the pump.On September 5, 2007 Since the 1 B pump was out of service for maintenance and the 1 C breaker had failed to close, the licensee needed to start the remaining CCW pump, the 1A. Upon attempting to start the 1A CCW pump, its Allis-Chalmers breaker failed to close, but, as it turned out, for a un-related reason.>>> Karen Cotton 09/19/2007 7:36 AM >>>Thanks, Karen CC: Mike Franovich; Robert Martin S"13 |
| | [Karen Cotton-l-arley All NRC sIIdesSUAUYlYU(.ppt Page 1 SKaren Cotton -F-arley All NRC slidesSDA091907.pt Page! l U.S.NRC UNITED STATES NUCLEAR REGULATORY COMMISSION Protecting People and the Environment Senate Committee on Environment and Public Works Briefing September 19, 2007 1 J[a:r7bC tton _-_F !r16TAITIRJRC s @i~sýSO~A0 907 te__ a NRC Staff" Headquarters |
| | -David Decker -Congressional Affairs-Timothy McGinty -Nuclear Reactor Regulation (NRR), Deputy Director of Division of Operating Reactor Licensing (DORL)-Stephen Alexander |
| | -NRR, PRA Operations Support;& Maintenance Branch, Augmented Inspection Team (AIT) Member-Karen Cotton -NRR, DORL, Joseph M. Farley Nuclear Plant -Project Manager* Region II-Scott Shaeffer -Chief, Reactor Projects Branch 2-Michael Ernstes -Chief, Training and Development Branch, AIT Leader 2 |
| | ~Kai~FCotton |
| | -F~iI~AITN Rt~IidesSDA09 1907. p~p~ Page 3 1j, "ar ý_Cotto--n,----"arýy-ITNRG sIidesSDA091907.pRt",,................ |
| | Joseph M. Farley Nuclear Plant Operator -Southern Nuclear Operating Company Type -Westinghouse; PWR;3-loop* Units-Two* Unit 1 -830 MWt* Unit 2- ,839 MWt 3 I H kai:6_n'C6tt6n |
| | -Fariev AITNR(; slidesSDA091907.ppt Pae4I I Karen Cotton -Farlev AITNRC sIidesSDAO9l9O7.ppt Page 4~l I'r"--US.NRC History of events On May 3, 2007 The U.S. Nuclear Regulatory Commission completed a supplemental inspection regarding the Cooling Water Systems.-several significant weaknesses were identified regarding: |
| | -evaluations for repeat safety-related breaker failures* the thoroughness of design modification reviews for the installation of new breakers 4 Karen Cotton -Farley AITNRC siidesSDAO9l9O-7 .pp t Page 5 (7. U1.S.NRC History of events On September 4, 2007* In support of planned maintenance on the 1 B component cooling water (CCW) pump, the licensee needed to start another pump." The Cutler-Hammer breaker for the 10 CCW pump failed to close when the licensee attempted to start the pump.On September 5, 2007* Since the 1 B pump was out of service for maintenance and the 1C breaker had failed to close, the licensee needed to start the remaining CCW pump, the 1A. Upon attempting to start the 1A CCW pump, its Allis-Chalmers breaker failed to close, but, as it turned out, for a un-related reason.5 I RC lid-Page 6 11 K~i~n Cotton -Fa~I AITt~.1~C |
| | ~ Page 6 I I ~ ~ ~jýU. S.N RC Augmented Inspection Team" The previous events precipitated the formation of an Augmented Inspection Team" The team was chartered on September 10, 2007 6 KaCotton -tage Next Steps Public Exit Meeting; September 20, 2007 at the site NRC will continue to:-Confirm root cause analysis and extent of condition-Evaluate potential findings or violations |
| | -Monitor interim and long-term corrective action for the identified breaker. problems Develop AIT Inspection Report 7}} |
Revision as of 17:48, 10 November 2018
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Category:E-Mail
MONTHYEARML24227A0512024-08-14014 August 2024 August 14, 2024 - Request for Additional Information - Farley, Units 1 and 2 - Proposed LAR to Revise TS SR 3.6.6.8 Frequency ML24212A2232024-07-30030 July 2024 Acceptance Review - License Amendment Request to Adopt TSTF-500, Rev 2 DC Electrical Rewrite (EPID L-2024-LLA-0091) - Email ML24205A2142024-07-23023 July 2024 Acceptance Review - License Amendment Request to Change TS 3.6.5, Containment Air Temperature ML24197A1572024-07-15015 July 2024 NRR E-mail Capture - Acceptance Review - Farley and Vogtle 1 and 2, LAR - TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24197A0172024-07-12012 July 2024 NRR E-mail Capture - Fyi - Acceptance Review - Farley and Vogtle 1 and 2 - Alternative Request for Pressurizer Welds ML24194A0032024-07-11011 July 2024 NRR E-mail Capture - Fyi - Acceptance Review - Farley, Hatch, and Vogtle 1 and 2 - Alternative Request for Code Case N-572 ML24180A0012024-06-26026 June 2024 NRR E-mail Capture - Acceptance Review Farley 1 and 2 and Vogtle 1 and 2 - Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) (L-2024-LLR-0041) ML24170A9362024-06-18018 June 2024 NRR E-mail Capture - Fyi - Change to Estimated Completion Date for the SNC Fleet Physical Barrier Exemptions (L-2023-LLE-0018 and L-2023-LLE-0021) ML24142A4992024-05-21021 May 2024 NRR E-mail Capture - Acceptance Review - Farley and Hatch - LAR to Revise TS 1.1 and Add Online Monitoring (OLM) Program (L-2024-LLA-0058) ML24114A2452024-04-23023 April 2024 Acceptance Review - Farley, Units 1 and 2-Proposed LAR to Revise TS SR 3.6.6.8 ML24037A1352024-02-0505 February 2024 e-mail ML23335A0122023-12-0101 December 2023 FNP - IP95001 Inspection Notification and Request for Information (Email to Farley) ML23243A9952023-08-31031 August 2023 Request for Baseline RP Inspection ML23236A0022023-08-22022 August 2023 NRR E-mail Capture - Request for Additional Information - Farley, Units 1&2, Emergency TS 3.6.5 LAR ML23223A0142023-08-10010 August 2023 NRR E-mail Capture - Acceptance Review - SNC Fleet Exemption to 10 CFR 73.2, Physical Barriers ML23198A1552023-07-17017 July 2023 NRR E-mail Capture - for Your Action - Request for Additional Information (RAI) - Hatch, Farley, and Vogtle, Units 1 and 2 Quality Assurance Topical Report (QATR) Submittal Dated June 15, 2023 ML23135A0922023-05-11011 May 2023 NRR E-mail Capture - Acceptance Review - SNC Fleet Request to Use Specific Provision of a Later Edition of the ASME BPV Code, Section XI (L-2023-LLR-0016) ML23095A0832023-04-0505 April 2023 NRR E-mail Capture - for Your Action - RAI - Farley - Containment Isolation Valves, Surveillance Requirement 3.6.3.5 LAR (L-2022-LLA-0189) ML23086A0232023-03-24024 March 2023 NRR E-mail Capture - for Your Action - Draft RAIs - Farley Surveillance Requirement (SR) 3.6.3.5 License Amendment Request (LAR) (L-2022-LLA-0189) ML23073A0252023-03-13013 March 2023 NRR E-mail Capture - Fyi - Closeout the Evacuation Time Estimate (ETE) Reviews for SNC Fleet ML23045A0782023-02-13013 February 2023 NRR E-mail Capture - Fyi - Revised Estimated Hours - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML23009A0152023-01-0606 January 2023 NRR E-mail Capture - Acceptance Review - Farley Surveillance Requirement (SR) 3.6.3.5 LAR ML23009A0062023-01-0606 January 2023 NRR E-mail Capture - Corrected - Acceptance Review - Farley Surveillance Requirement (SR) 3.6.3.5 LAR ML23003A8092023-01-0303 January 2023 NRR E-mail Capture - for Your Action - RAI - Farley - ISI Alternative FNP-ISI-ALT-05-05 (L-2022-LLR-0068) ML22354A0112022-12-19019 December 2022 NRR E-mail Capture - Acceptance Review - Requested Licensing Action Regarding TS Revision to Adopt WCAP-17661-P-A, Improved Relaxed Axial Offset Control and Constant Axial Offset Control Fq Surveillance TS (L-2022-LLA-0148 and L-2022-LLA-01 ML22334A1482022-11-30030 November 2022 NRR E-mail Capture - for Your Action - RAI - Farley - TS 3.4.10 LAR, Psv Setpoint (L-2022-LLA-0098) ML22285A2532022-10-12012 October 2022 NRR E-mail Capture - Acceptance Review - Farley Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 ML22285A0082022-10-11011 October 2022 NRR E-mail Capture - Acceptance Review - Farley TS 4.3 LAR (L-2022-LLA-0138) ML22229A4792022-08-15015 August 2022 HP Baseline Inspection Document Request ML22213A2692022-08-0101 August 2022 NRR E-mail Capture - Joseph M. Farley Nuclear Plant Units 1 and 2 - Acceptance of Requested Licensing Action Revise Technical Specification 3.4.10, Pressurizer Safety Valves ML22123A1782022-05-0303 May 2022 NRR E-mail Capture - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22123A1802022-05-0303 May 2022 NRR E-mail Capture - Correction - RAIs for Farley LAR Re. TS 5.5.17 Containment Leakage Rate Testing Program ML22112A0892022-04-22022 April 2022 NRR E-mail Capture - Draft RAIs for Farley LAR Re. TS 5.5.17 ML22104A1312022-04-14014 April 2022 NRR E-mail Capture - Request for Additional Information - Farley and Vogtle - Relocate Piping Inspection License Amendment Request (L-2021-LLA-0235) ML22018A0272022-01-18018 January 2022 2022 All RFI Responses - Exercise and Program Inspections - Revl ML22020A0662022-01-13013 January 2022 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TSTF-269-A LAR (L-2021-LLA-0234) ML22012A0632022-01-11011 January 2022 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TS 5.5.16 LAR (L-2021-LLA-0235) ML22010A2402022-01-10010 January 2022 NRR E-mail Capture - Farley 1 and 2 - Acceptance of Requested Licensing Action Revise TS 5.5.17, Containment Leakage Rate Testing Program to Increase Calculated Peak Containment Pressure ML21321A3772021-11-16016 November 2021 NRR E-mail Capture - RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21321A3752021-11-10010 November 2021 NRR E-mail Capture - Draft RAIs for Farley LAR Sump Recirculation Valve Encapsulation Vessel Removal ML21292A1562021-10-19019 October 2021 NRR E-mail Capture - Acceptance Review - SNC Operating Fleet TSTF-554 LAR ML21274A0462021-10-0101 October 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle TSTF-577 LAR (L-2021-LLA-0163) ML21236A3142021-08-24024 August 2021 NRR E-mail Capture - Joseph M. Farley Nuclear Plant Units 1 and 2 - Acceptance of Requested Licensing Action Amendment to Remove Sump Recirculation Valve Encapsulation ML21180A2002021-06-28028 June 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle - Voluntary License Amendment Request to Use Beacon Power Distribution Monitoring System (L-2021-LLA-0109) ML21174A1182021-06-23023 June 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet - Remove Table of Contents LAR (L-2021-LLA-0115) ML21174A1152021-06-23023 June 2021 NRR E-mail Capture - Acceptance Review - Farley and Vogtle Exemption Requests from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (L-2021-LLE-0031) ML21132A0132021-05-11011 May 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet QATR Reduction in Commitment Licensing Action - L-2021-LLQ-0002 ML21105A0132021-04-14014 April 2021 NRR E-mail Capture - Acceptance Review - SNC Fleet LAR to Change TS 5.7, High Radiation Area (L-2021-LLA-0052) ML21012A3242021-01-12012 January 2021 NRR E-mail Capture - Request for Additional Information - Farley, 1 and 2 - Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML20351A4042020-12-16016 December 2020 NRR E-mail Capture - Draft RAIs for Farley 50.69 (ML20170B114) 2024-08-14
[Table view] Category:Slides and Viewgraphs
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 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 ML16260A1162016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides NL-16-0388, September 22, 2016, Public Meeting Presentation Slides2016-09-22022 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 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) 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) 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) 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 2024-09-23
[Table view] |
Text
~Karen Cot~ton -Re:FiýNnalc6py FarleyTR sl~ espt ae1 Pa e-l'3 From: David Decker To: Karen Cotton; Lauren Quinones; Michael Ernstes; Scott Shaeffer; Stephen Alexander; Tim McGinty Date: 09/19/2007 10:07:22 AM
Subject:
Re: Final copy Farley AITNRC slides.ppt The updates you suggest look good to me. Thanks. -David>>> Stephen Alexander 09/19/2007 10:00 AM >>>Again, in my view, the short version language will be a bit confusing to laymen. Attached is a suggested version -not longer -not to worry -but simpler language.
It reads as follows: On September 4, 2007 In support of planned maintenance on the 1 B component cooling water (CCW) pump, the licensee needed to start another pump.The Cutler-Hammer breaker for the IC CCW pump failed to close when the licensee attempted to start the pump.On September 5, 2007 Since the 1 B pump was out of service for maintenance and the 1 C breaker had failed to close, the licensee needed to start the remaining CCW pump, the 1A. Upon attempting to start the 1A CCW pump, its Allis-Chalmers breaker failed to close, but, as it turned out, for a un-related reason.>>> Karen Cotton 09/19/2007 7:36 AM >>>Thanks, Karen CC: Mike Franovich; Robert Martin S"13
[Karen Cotton-l-arley All NRC sIIdesSUAUYlYU(.ppt Page 1 SKaren Cotton -F-arley All NRC slidesSDA091907.pt Page! l U.S.NRC UNITED STATES NUCLEAR REGULATORY COMMISSION Protecting People and the Environment Senate Committee on Environment and Public Works Briefing September 19, 2007 1 J[a:r7bC tton _-_F !r16TAITIRJRC s @i~sýSO~A0 907 te__ a NRC Staff" Headquarters
-David Decker -Congressional Affairs-Timothy McGinty -Nuclear Reactor Regulation (NRR), Deputy Director of Division of Operating Reactor Licensing (DORL)-Stephen Alexander
-NRR, PRA Operations Support;& Maintenance Branch, Augmented Inspection Team (AIT) Member-Karen Cotton -NRR, DORL, Joseph M. Farley Nuclear Plant -Project Manager* Region II-Scott Shaeffer -Chief, Reactor Projects Branch 2-Michael Ernstes -Chief, Training and Development Branch, AIT Leader 2
~Kai~FCotton
-F~iI~AITN Rt~IidesSDA09 1907. p~p~ Page 3 1j, "ar ý_Cotto--n,----"arýy-ITNRG sIidesSDA091907.pRt",,................
Joseph M. Farley Nuclear Plant Operator -Southern Nuclear Operating Company Type -Westinghouse; PWR;3-loop* Units-Two* Unit 1 -830 MWt* Unit 2- ,839 MWt 3 I H kai:6_n'C6tt6n
-Fariev AITNR(; slidesSDA091907.ppt Pae4I I Karen Cotton -Farlev AITNRC sIidesSDAO9l9O7.ppt Page 4~l I'r"--US.NRC History of events On May 3, 2007 The U.S. Nuclear Regulatory Commission completed a supplemental inspection regarding the Cooling Water Systems.-several significant weaknesses were identified regarding:
-evaluations for repeat safety-related breaker failures* the thoroughness of design modification reviews for the installation of new breakers 4 Karen Cotton -Farley AITNRC siidesSDAO9l9O-7 .pp t Page 5 (7. U1.S.NRC History of events On September 4, 2007* In support of planned maintenance on the 1 B component cooling water (CCW) pump, the licensee needed to start another pump." The Cutler-Hammer breaker for the 10 CCW pump failed to close when the licensee attempted to start the pump.On September 5, 2007* Since the 1 B pump was out of service for maintenance and the 1C breaker had failed to close, the licensee needed to start the remaining CCW pump, the 1A. Upon attempting to start the 1A CCW pump, its Allis-Chalmers breaker failed to close, but, as it turned out, for a un-related reason.5 I RC lid-Page 6 11 K~i~n Cotton -Fa~I AITt~.1~C
~ Page 6 I I ~ ~ ~jýU. S.N RC Augmented Inspection Team" The previous events precipitated the formation of an Augmented Inspection Team" The team was chartered on September 10, 2007 6 KaCotton -tage Next Steps Public Exit Meeting; September 20, 2007 at the site NRC will continue to:-Confirm root cause analysis and extent of condition-Evaluate potential findings or violations
-Monitor interim and long-term corrective action for the identified breaker. problems Develop AIT Inspection Report 7