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| | number = ML112270513 | | | number = ML112270513 |
| | issue date = 08/15/2011 | | | issue date = 08/15/2011 |
| | title = Joseph M. Farley Nuclear Plant, Final Significance Determination of a Green Finding (NRC Inspection Report 05000348/2011013 and 05000364/2011013) | | | title = Final Significance Determination of a Green Finding (NRC Inspection Report 05000348/2011013 and 05000364/2011013) |
| | author name = Croteau R P | | | author name = Croteau R |
| | author affiliation = NRC/RGN-II/DRP | | | author affiliation = NRC/RGN-II/DRP |
| | addressee name = Stinson L M | | | addressee name = Stinson L |
| | addressee affiliation = Southern Nuclear Operating Co, Inc | | | addressee affiliation = Southern Nuclear Operating Co, Inc |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
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| =Text= | | =Text= |
| {{#Wiki_filter: | | {{#Wiki_filter:UNITED STATES August 15, 2011 |
| [[Issue date::August 15, 2011]]
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| EA-11-112 Mr. L. Michael Stinson Vice President - Farley Southern Nuclear Operating Company, Inc. 7388 North State Highway 95 Columbia, AL 36319
| | ==SUBJECT:== |
| | JOSEPH M. FARLEY NUCLEAR PLANT, FINAL SIGNIFICANCE DETERMINATION OF A GREEN FINDING (NRC INSPECTION REPORT 05000348/2011013 AND 05000364/2011013) |
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| SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, FINAL SIGNIFICANCE DETERMINATION OF A GREEN FINDING (NRC INSPECTION REPORT 05000348/2011013 AND 05000364/2011013)
| | ==Dear Mr. Stinson:== |
| | The purpose of this letter is to provide you the final results of our significance determination of the preliminary White finding (i.e., a finding with low to moderate increased safety significance) |
| | discussed in NRC Inspection Report No. 05000348/2011-012 and 05000364/2011-012, dated June 8, 2011 (ADAMS Accession # ML111590912). The Initiating Events Cornerstone inspection finding (identified as AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch) was assessed using the Significance Determination Process (SDP) and was preliminarily characterized as White. The finding involved the failure to maintain the configuration of the 1A reactor coolant pump (RCP) oil lift pump system in accordance with plant design and drawings. This resulted in an electrical short on November 10, 2010 that caused a small fire on the Unit 1 main control room (MCR) 1A RCP board handswitch. The fire was quickly identified by control room operators during an attempt to operate the RCP oil lift pump, and promptly extinguished by operators without the need for additional fire mitigation measures. |
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| | The finding affected both units due to the common control room. The finding was assigned a cross-cutting aspect in the Work Practices component of the Human Performance area in that personnel proceeded in the face of uncertainty or unexpected circumstances during preventative maintenance activities and did not properly preplan work activities for identified corrective maintenance. [H.4(a)] |
| | At your request, a Regulatory Conference was held on July 12, 2011, to discuss your views on this issue. A meeting summary was issued on July 15, 2011, which included copies of the slide presentation made by Southern Nuclear Operating Company (SNC) (ADAMS Accession # |
| | ML111960460). During the meeting, your staff described your assessment of the significance of the finding and the corrective actions taken to resolve it, including the root cause evaluation of the finding. SNC staff also discussed the circumstances surrounding the main control room fire and presented information, including handswitch testing, to support its contention that the fire should be considered a non-challenging fire per the subjective guidance of NUREG 6850, Fire PRA Methodology for Nuclear Power Plants. Additionally, your staff presented new information |
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| | SNC 2 to be considered in the final SDP analysis of the event. More specifically, SNC addressed the impact of the MCR ventilation on the decision to evacuate the MCR and the human performance reliability impact of performing safe shutdown activities in the event the MCR is evacuated. |
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| | The NRC evaluated the information you presented in the conference and determined the fire event, caused by the mis-wiring of the 1A RCP oil lift pump pressure switch, was still considered to be potentially challenging. The NRC concluded that if not suppressed, the fire could eventually lead to MCR evacuation. The basis for assuming the fire could be potentially challenging was the subjective classification criteria of NUREG-6850, Section C.3.3.2, including that this was a fire requiring active intervention to prevent spread and the possible heat release rates associated with a fire in this location, numerous cables could be in the zone of influence. |
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| | At the conference, SNC presented the results of handswitch testing, which was performed to understand whether the fire would self-extinguish and therefore limit the potential spread of the fire. The results of the tests did indicate that the types of electrical faults seen in the electrical short occurring November 10, 2010, tend to self-extinguish. The NRC determined that the test configuration and its results could provide limited perspective on the potential for MCR fire propagation. During the actual fire, an operator removed the light indication array which potentially changed the air flow and relative oxygen concentration at the fire location which was not done in the test configuration. Finally, there was not a definitive indication that could confirm operator intervention did not extinguish the fire. The information provided was not sufficient for the NRC to definitively conclude that the fire in the MCR would have self-extinguished. |
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| | Therefore, this fire was classified as Potentially Challenging for the purposes of evaluating this event via the SDP. |
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| | The NRC also evaluated new information presented by SNC regarding the impact of the MCR ventilation on the decision to evacuate the MCR. Based on this information, the NRC concluded that the ventilation would remain in operation throughout the fire. This reduces the number of fires from the family of heat release rates of single cable fires that would require control room evacuation. Additionally, the information indicates that some time delay is warranted in developing a single cable bundle fire which increases the time available to extinguish a fire before evacuation would be required. Based on the new information presented by SNC at the conference, the NRC concluded that a reduction in the frequency of fires requiring MCR evacuation, and a corresponding reduction in the probability of MCR abandonment, was warranted. |
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| | After considering the information you provided at the regulatory conference, the NRC has concluded that the finding is appropriately characterized as Green, a finding of very low safety significance. The NRC also has determined that the finding is a violation of Technical Specification 5.4.1 as discussed in inspection report 05000348/2011-012 and 05000364/2011-012. The circumstances surrounding the violation was described in detail that inspection report. |
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| | Because this violation was of very low safety significance and it was entered into the licensees corrective action program as CR 2010116613, this violation is being treated as an NCV, consistent with the Enforcement Policy. NCV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch. |
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| | SNC 3 For administrative purposes, this letter is issued as NRC Inspection Report No. |
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| ==Dear Mr. Stinson:==
| | 05000348/2011013 and 05000364/2011013. Accordingly, AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch are updated consistent with the regulatory positions described in this letter. Therefore: AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch, is updated as NCV 05000348,364/2011012-01 with a safety significance of Green and cross-cutting aspect in the Work Practices component of the Human Performance area [H.4(a)]. |
| The purpose of this letter is to provide you the final results of our significance determination of the preliminary White finding (i.e., a finding with low to moderate increased safety significance) discussed in NRC Inspection Report No. 05000348/2011-012 and 05000364/2011-012, dated June 8, 2011 (ADAMS Accession # ML111590912). The Initiating Events Cornerstone inspection finding (identified as AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch) was assessed using the Significance Determination Process (SDP) and was preliminarily characterized as White. The finding involved the failure to maintain the configuration of the 1A reactor coolant pump (RCP) oil lift pump system in accordance with plant design and drawings. This resulted in an electrical short on November 10, 2010 that caused a small fire on the Unit 1 main control room (MCR) 1A RCP board handswitch. The fire was quickly identified by control room operators during an attempt to operate the RCP oil lift pump, and promptly extinguished by operators without the need for additional fire mitigation measures. The finding affected both units due to the common control room. The finding was assigned a cross-cutting aspect in the Work Practices component of the Human Performance area in that personnel proceeded in the face of uncertainty or unexpected circumstances during preventative maintenance activities and did not properly preplan work activities for identified corrective maintenance. [H.4(a)] At your request, a Regulatory Conference was held on July 12, 2011, to discuss your views on this issue. A meeting summary was issued on July 15, 2011, which included copies of the slide presentation made by Southern Nuclear Operating Company (SNC) (ADAMS Accession #
| | The NRC has concluded that the information regarding the reason for the violation the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in inspection report 05000348/2011-012 and 05000364/2011-012. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position. |
| ML111960460). During the meeting, your staff described your assessment of the significance of the finding and the corrective actions taken to resolve it, including the root cause evaluation of the finding. SNC staff also discussed the circumstances surrounding the main control room fire and presented information, including handswitch testing, to support its contention that the fire should be considered a non-challenging fire per the subjective guidance of NUREG 6850, Fire PRA Methodology for Nuclear Power Plants. Additionally, your staff presented new information SNC 2 to be considered in the final SDP analysis of the event. More specifically, SNC addressed the impact of the MCR ventilation on the decision to evacuate the MCR and the human performance reliability impact of performing safe shutdown activities in the event the MCR is evacuated.
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| | You have 30 calendar days from the date of this letter to appeal the staffs significance determination for the Green finding or the NCV. An appeal of the Green finding will be considered to have merit only if it meets the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2. |
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| | Additionally, if you disagree with the cross-cutting aspect assigned to the finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Joseph M. Farley Nuclear Plant. |
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| | In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, Enclosure 1, and your response (if you choose to provide one), will be made available electronically for public inspection in the NRC Public Document Room or from ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. However, because of the security-related information contained in Enclosure 2, and in accordance with 10 CFR 2.390, a copy of Enclosure 2 will not be available for public inspection. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction. |
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| | Sincerely, |
| | /RA/ |
| | Richard P. Croteau, Director Division of Reactor Projects Docket No.: 50-348, 50-364 License No.: NPF-2, NPF-8 cc: (See page 4) |
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| | ___ML112270513__ |
| | OFFICE RII:DRP RII:DRP RII:DRP RII:DRS RII:EICS RII:DRP SIGNATURE Via email Via email Via email Via telecom SES /RA/ SMS /RA/ |
| | NAME TLighty ECrowe JSowa WRogers SSparks SShaeffer DATE 08/15/2011 08/15/2011 08/15/2011 08/11/2011 08/15/2011 0815/2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO |
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| | SNC 4 cc w/encl: |
| | B. D. McKinney, Jr. J. L. Pemberton Regulatory Response Manager SVP & General Counsel-Ops & SNC Southern Nuclear Operating Company, Inc. Southern Nuclear Operating Company, Inc. |
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| | Electronic Mail Distribution Electronic Mail Distribution M. J. Ajluni Chris Clark Nuclear Licensing Director Commissioner Southern Nuclear Operating Company, Inc. Georgia Department of Natural Resources Electronic Mail Distribution Electronic Mail Distribution T. D. Honeycutt John G. Horn Regulatory Response Supervisor Site Support Manager Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant Electronic Mail Distribution Southern Nuclear Operating Company, Inc. |
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| The NRC evaluated the information you presented in the conference and determined the fire event, caused by the mis-wiring of the 1A RCP oil lift pump pressure switch, was still considered to be potentially challenging. The NRC concluded that if not suppressed, the fire could eventually lead to MCR evacuation. The basis for assuming the fire could be potentially challenging was the subjective classification criteria of NUREG-6850, Section C.3.3.2, including that this was a fire requiring active intervention to prevent spread and the possible heat release rates associated with a fire in this location, numerous cables could be in the zone of influence. At the conference, SNC presented the results of handswitch testing, which was performed to understand whether the fire would self-extinguish and therefore limit the potential spread of the fire. The results of the tests did indicate that the types of electrical faults seen in the electrical short occurring November 10, 2010, tend to self-extinguish. The NRC determined that the test configuration and its results could provide limited perspective on the potential for MCR fire propagation. During the actual fire, an operator removed the light indication array which potentially changed the air flow and relative oxygen concentration at the fire location which was not done in the test configuration. Finally, there was not a definitive indication that could confirm operator intervention did not extinguish the fire. The information provided was not sufficient for the NRC to definitively conclude that the fire in the MCR would have self-extinguished. Therefore, this fire was classified as "Potentially Challenging" for the purposes of evaluating this event via the SDP. The NRC also evaluated new information presented by SNC regarding the impact of the MCR ventilation on the decision to evacuate the MCR. Based on this information, the NRC concluded that the ventilation would remain in operation throughout the fire. This reduces the number of fires from the family of heat release rates of single cable fires that would require control room evacuation. Additionally, the information indicates that some time delay is warranted in developing a single cable bundle fire which increases the time available to extinguish a fire before evacuation would be required. Based on the new information presented by SNC at the conference, the NRC concluded that a reduction in the frequency of fires requiring MCR evacuation, and a corresponding reduction in the probability of MCR abandonment, was warranted.
| | Electronic Mail Distribution Todd L. Youngblood Plant Manager Ted V. Jackson Joseph M. Farley Nuclear Plant Emergency Response and Radiation Electronic Mail Distribution Program Manager Environmental Protection Division L. P. Hill Georgia Department of Natural Resources Licensing Supervisor Electronic Mail Distribution Southern Nuclear Operating Company, Inc. |
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| After considering the information you provided at the regulatory conference, the NRC has concluded that the finding is appropriately characterized as Green, a finding of very low safety significance. The NRC also has determined that the finding is a violation of Technical Specification 5.4.1 as discussed in inspection report 05000348/2011-012 and 05000364/2011-012. The circumstances surrounding the violation was described in detail that inspection report. Because this violation was of very low safety significance and it was entered into the licensee's corrective action program as CR 2010116613, this violation is being treated as an NCV, consistent with the Enforcement Policy. NCV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch.
| | Electronic Mail Distribution Tom W. Pelham Performance Improvement Supervisor Jeffrey T. Gasser Joseph M. Farley Nuclear Plant Chief Nuclear Officer Southern Nuclear Operating Company, Inc. |
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| SNC 3 For administrative purposes, this letter is issued as NRC Inspection Report No. 05000348/2011013 and 05000364/2011013. Accordingly, AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch are updated consistent with the regulatory positions described in this letter. Therefore: AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch, is updated as NCV 05000348,364/2011012-01 with a safety significance of Green and cross-cutting aspect in the Work Practices component of the Human Performance area [H.4(a)]. The NRC has concluded that the information regarding the reason for the violation the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in inspection report 05000348/2011-012 and 05000364/2011-012. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position. You have 30 calendar days from the date of this letter to appeal the staff's significance determination for the Green finding or the NCV. An appeal of the Green finding will be considered to have merit only if it meets the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2. Additionally, if you disagree with the cross-cutting aspect assigned to the finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Joseph M. Farley Nuclear Plant. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, Enclosure 1, and your response (if you choose to provide one), will be made available electronically for public inspection in the NRC Public Document Room or from ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. However, because of the security-related information contained in Enclosure 2, and in accordance with 10 CFR 2.390, a copy of Enclosure 2 will not be available for public inspection. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
| | Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Electronic Mail Distribution Cynthia A. Sanders R. L. Gladney Radioactive Materials Program Manager Licensing Engineer Environmental Protection Division Southern Nuclear Operating Company, Inc. Georgia Department of Natural Resources Electronic Mail Distribution Electronic Mail Distribution N. J. Stringfellow James C. Hardeman Licensing Manager Environmental Radiation Program Manager Southern Nuclear Operating Company, Inc. Environmental Protection Division Electronic Mail Distribution Georgia Department of Natural Resources Electronic Mail Distribution Paula Marino Vice President William D. Oldfield Engineering Principal Licensing Engineer Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant Electronic Mail Distribution Electronic Mail Distribution (cc continued next page) |
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| Sincerely,/RA/ Richard P. Croteau, Director Division of Reactor Projects Docket No.: 50-348, 50-364 License No.: NPF-2, NPF-8 cc: (See page 4)
| | SNC 5 (cc continued) |
| SNC 3 For administrative purposes, this letter is issued as NRC Inspection Report No.
| | Mr. Mark Culver Chairman Houston County Commission P. O. Box 6406 Dothan, AL 36302 James A. Sommerville Program Coordination Branch Chief Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 L. L. Crumpton Administrative Assistant, Sr. |
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| 05000348/2011013 and 05000364/2011013. Accordingly, AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch are updated consistent with the regulatory positions described in this letter. Therefore: AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch, is updated as NCV 05000348,364/2011012-01 with a safety significance of Green and cross-cutting aspect in the Work Practices component of the Human Performance area [H.4(a)]. The NRC has concluded that the information regarding the reason for the violation the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in inspection report 05000348/2011-012 and 05000364/2011-012. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position. You have 30 calendar days from the date of this letter to appeal the staff's significance determination for the Green finding or the NCV. An appeal of the Green finding will be considered to have merit only if it meets the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2. Additionally, if you disagree with the cross-cutting aspect assigned to the finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Joseph M. Farley Nuclear Plant. In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, Enclosure 1, and your response (if you choose to provide one), will be made available electronically for public inspection in the NRC Public Document Room or from ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. However, because of the security-related information contained in Enclosure 2, and in accordance with 10 CFR 2.390, a copy of Enclosure 2 will not be available for public inspection. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
| | Southern Nuclear Operating Company, Inc. |
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| Sincerely,/RA/ Richard P. Croteau, Director Division of Reactor Projects Docket No.: 50-348, 50-364 License No.: NPF-2, NPF-8 cc: (See page 4) X PUBLICLY AVAILABLE G NON-PUBLICLY AVAILABLE G SENSITIVE X NON-SENSITIVE ADAMS: G Yes ACCESSION NUMBER:___ML112270513__ OFFICE RII:DRP RII:DRP RII:DRP RII:DRS RII:EICS RII:DRP SIGNATURE Via email Via email Via email Via telecom SES /RA/ SMS /RA/ NAME TLighty ECrowe JSowa WRogers SSparks SShaeffer DATE 08/15/2011 08/15/2011 08/15/2011 08/11/2011 08/15/2011 0815/2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO OFFICIAL RECORD COPY DOCUMENT NAME: G:\DRPII\RPB2\FARLEY\FLAMING HANDSWITCH\2011-013 RCP HANDSWITCH FIRE FSD LETTER FINAL.DOCX SNC 4 cc w/encl: B. D. McKinney, Jr. Regulatory Response Manager Southern Nuclear Operating Company, Inc. Electronic Mail Distribution M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. Electronic Mail Distribution T. D. Honeycutt Regulatory Response Supervisor Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Todd L. Youngblood Plant Manager Joseph M. Farley Nuclear Plant Electronic Mail Distribution L. P. Hill Licensing Supervisor Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Jeffrey T. Gasser Chief Nuclear Officer Southern Nuclear Operating Company, Inc. Electronic Mail Distribution R. L. Gladney Licensing Engineer Southern Nuclear Operating Company, Inc. Electronic Mail Distribution N. J. Stringfellow Licensing Manager Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Paula Marino Vice President Engineering Southern Nuclear Operating Company, Inc. Electronic Mail Distribution J. L. Pemberton SVP & General Counsel-Ops & SNC Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Chris Clark Commissioner Georgia Department of Natural Resources Electronic Mail Distribution John G. Horn Site Support Manager Joseph M. Farley Nuclear Plant Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Ted V. Jackson Emergency Response and Radiation Program Manager Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution Tom W. Pelham Performance Improvement Supervisor Joseph M. Farley Nuclear Plant Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Cynthia A. Sanders Radioactive Materials Program Manager Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution James C. Hardeman Environmental Radiation Program Manager Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution William D. Oldfield Principal Licensing Engineer Joseph M. Farley Nuclear Plant Electronic Mail Distribution (cc continued next page)
| | Electronic Mail Distribution F. Allen Barnes Director Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution |
| SNC 5 (cc continued) Mr. Mark Culver Chairman Houston County Commission P. O. Box 6406 Dothan, AL 36302 James A. Sommerville Program Coordination Branch Chief Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 L. L. Crumpton Administrative Assistant, Sr. Southern Nuclear Operating Company, Inc. Electronic Mail Distribution F. Allen Barnes Director Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution SNC 6 Letter to L. Michael Stinson from Richard P. Croteau dated August 15, 2011
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| SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, FINAL SIGNIFICANCE DETERMINATION OF A GREEN FINDING (NRC INSPECTION REPORT 05000348/2011013 AND 05000364/2011013) Distribution w/encl: RidsNrrPMFarley Resource C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC | | SNC 6 Letter to L. Michael Stinson from Richard P. Croteau dated August 15, 2011 SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, FINAL SIGNIFICANCE DETERMINATION OF A GREEN FINDING (NRC INSPECTION REPORT 05000348/2011013 AND 05000364/2011013) |
| | Distribution w/encl: |
| | RidsNrrPMFarley Resource C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC |
| }} | | }} |
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Category:Inspection Report
MONTHYEARIR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 IR 05000348/20230112023-04-13013 April 2023 Biennial Problem Identification and Resolution Inspection Report 05000348/2023011 and 05000364/2023011 IR 05000348/20234012023-03-31031 March 2023 Security Baseline Inspection Report 05000348/2023401 and 05000364/2023401 IR 05000348/20220062023-03-0101 March 2023 Annual Assessment Letter for Joseph M. Farley Nuclear Plant, Units 1 and 2 Report 05000348/2022006 and 05000364/2022006 IR 05000348/20220112023-02-16016 February 2023 NRC Inspection Report 05000348/2022011 IR 05000348/20220902023-02-16016 February 2023 NRC Inspection Report 05000348/2022090 IR 05000348/20220042023-01-23023 January 2023 Integrated Inspection Report 05000348/2022004 and 05000364/2022004 ML22343A0382022-12-13013 December 2022 Notification of Joseph M. Farley Nuclear Plant Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 IR 05000348/20224042022-11-29029 November 2022 Security Baseline Inspection Report 05000348/2022404 and 05000364/2022404 IR 05000348/20224402022-11-0707 November 2022 Special Inspection Report 05000348/2022440 and 05000364/ 2022440 and Preliminary Greater than Green Finding and and Apparent Violation (Cover Letter) IR 05000348/20220032022-10-28028 October 2022 Integrated Inspection Report 05000348/2022003 and 05000364/2022003 IR 05000348/20220502022-09-30030 September 2022 Special Inspection Reactive Report 05000348/2022050 and Apparent Violation IR 05000348/20220052022-08-24024 August 2022 Updated Inspection Plan for Joseph M. Farley Nuclear Plant, Units 1 and 2 - Report 05000348/2022005 and 05000364/2022005 IR 05000348/20220022022-08-12012 August 2022 Integrated Inspection Report 05000348/2022002 and 05000364/2022002 ML22214B8262022-08-0404 August 2022 Security Baseline Inspection Report 05000348/2022403 and 05000364/2022403 IR 05000348/20233012022-08-0101 August 2022 Notification of Licensed Operator Initial Examination 05000348/2023301 and 05000364/2023301 IR 05000348/20224022022-07-26026 July 2022 Security Baseline Inspection Report 05000348/2022402 and 05000364/2022402 IR 05000348/20224012022-05-0606 May 2022 Cyber Security Inspection Report 05000348/2022401 and 05000364/2022401 IR 05000348/20220012022-05-0404 May 2022 Integrated Inspection Report 05000348/2022001 and 05000364/2022001 IR 05000348/20220102022-03-22022 March 2022 Triennial Inspection of Evaluation of Changes, Tests and Experiments Baseline Inspection Report 05000348/2022010 and 05000364/2022010 IR 05000348/20210062022-03-0202 March 2022 Annual Assessment Letter for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report No. 05000348/2021006 and 05000364/2021006) IR 05000348/20210042022-02-0808 February 2022 Integrated Inspection Report 05000348/2021004 and 05000364/2021004 IR 05000348/20210112021-12-13013 December 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000348/2021011 and 05000364/2021011 ML21347A4422021-12-13013 December 2021 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000348/2022401; 05000364/2022401 IR 05000348/20214032021-12-0202 December 2021 Security Baseline Inspection Report 05000348/2021403 and 05000364/2021403 IR 05000348/20210032021-11-10010 November 2021 Integrated Inspection Report 05000348/2021003, 05000364/2021003, and 07200042/2021001 IR 05000348/20214022021-09-15015 September 2021 Security Baseline Inspection Report 05000348/2021402 and 05000364/2021402 IR 05000348/20210052021-08-24024 August 2021 Updated Inspection Plan for Joseph M. Farley Nuclear Plant Units 1 and 2 (Report 05000348/2021005 and 05000364/2021005) IR 05000348/20213012021-08-18018 August 2021 NRC Operator License Examination Report 05000348/2021301 and 05000364/2021301 IR 05000348/20210022021-07-30030 July 2021 Integrated Inspection Report 05000348/2021002 and 05000364/2021002 and Exercise of Enforcement Discretion IR 05000348/20210122021-07-19019 July 2021 Triennial Fire Protection Team Inspection (FPTI) Report 05000348/2021012 and 05000364/2021012 IR 05000324/20213642021-06-11011 June 2021 Exam Approval Letter 05000348/2021-301 and 05000324/2021-364 IR 05000348/20210012021-05-0404 May 2021 Integrated Inspection Report 05000348/2021001 and 05000364/2021001 IR 05000348/20214012021-04-0606 April 2021 Security Baseline Inspection Report 05000348/2021401 and 05000364/2021401 IR 05000348/20210102021-04-0505 April 2021 Biennial Problem Identification and Resolution Inspection Report 05000348/2021010 and 05000364/2021010 IR 05000348/20200062021-03-0303 March 2021 Annual Assessment Letter for Joseph M. Farley Nuclear Plant - Report 05000348/2020006 and 05000364/2020006 IR 05000348/20200042021-02-11011 February 2021 Integrated Inspection Report 05000348/2020004 and 05000364/2020004 and Independent Spent Fuel Storage Installation Report 07200042/2020003 IR 05000348/20200102021-01-14014 January 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000348/2020010 and 05000364/2020010 IR 05000348/20204032020-12-23023 December 2020 Security Baseline Inspection Report 05000348/2020403 and 05000364/2020403 2024-01-24
[Table view] Category:Letter
MONTHYEARML24010A0032024-01-30030 January 2024 Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24026A0532024-01-30030 January 2024 Notification of an NRC Fire Protection Team Inspection- (Report 05000348/2024011, 05000364/2024011) and Request for Information IR 05000348/20230402024-01-24024 January 2024 95001 Supplemental Inspection Report 05000348/2023040 and Follow-Up Assessment Letter ML23341A2042024-01-12012 January 2024 Request for Additional Information Exemption Requests for Physical Barriers (EPID L-2023-LLE-0018 & L-2023-LLE-0021) NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23345A1312024-01-0303 January 2024 Withholding Letter - SNC Fleet - Physical Barriers Exemption (L-2023-LLE-0018 and L-2023-LLE-0021) ML23346A2222023-12-22022 December 2023 Transmittal of Dam Inspection Report - Public NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation ML23228A1432023-11-22022 November 2023 Issuance of Amendment Nos. 249 and 246 to Revise TS 3.6.3, Surveillance Requirement 3.6.3.5 to Eliminate Event-Based Testing of Containment Purge Valves with Resilient Seals NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection ML23318A0672023-10-31031 October 2023 1 to Updated Final Safety Analysis Report, Updated NFPA 805 Fire Protection Program Design Basis Document, Technical Specification Bases Changes, Technical Requirements Manual Changes, IR 05000348/20230032023-10-24024 October 2023 Integrated Inspection Report 05000348/2023003 and 05000364/2023003 IR 05000348/20230912023-10-19019 October 2023 Final Significance Determination of a White Finding and Notice of Violation and Assessment Followup Letter NRC Inspection Report 05000348/2023091 IR 05000348/20234022023-10-18018 October 2023 Security Baseline Inspection Report 05000348/2023402 and 05000364/2023402 IR 05000348/20234412023-10-12012 October 2023 Supplemental Inspection Report 05000348/2023441 and 05000364/2023441 and Follow-Up Assessment Letter (Cover Letter) ML23241B0212023-09-12012 September 2023 Review of Quality Assurance Topical Report NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding IR 05000348/20230902023-08-31031 August 2023 NRC Inspection Report 05000348/2023090 and Preliminary White Finding and Apparent Violation ML23164A1202023-08-30030 August 2023 Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0, to the Requirements of the ASME Code ML23240A0012023-08-30030 August 2023 Correction to Issuance of Amendment Nos. 241, 242, 243, and 244 ML23235A2962023-08-24024 August 2023 Issuance of Amendment Nos. 247 and 244, Regarding License Amendment Request to Revise Technical Specification 3.6.5, Containment Air Temperature, (EPID L-2023-LLA-0116) (Emergency Circumstances) NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit IR 05000348/20330012023-08-14014 August 2023 NRC Operator License Examination Report 05000348/203301 and 05000364/2023302 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal IR 05000348/20230022023-08-10010 August 2023 Integrated Inspection Report 05000348/2023002 and 05000364/2023002, and Apparent Violation ML23221A3062023-08-0909 August 2023 Notification of NRC Supplemental Inspection (95002) and Request for Information (Cover Letter) NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis ML23202A1122023-08-0202 August 2023 Units, 1 and 2; and Vogtle Units 1 and 2 - Request to Use a Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications ML23136B1542023-07-0303 July 2023 Issuance of Amendment Nos. 246 & 243, Regarding License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated Spent Fuel Pool (SFP) Criticality Analysis IR 05000348/20230102023-06-29029 June 2023 Comprehensive Engineering Team Inspection (CETI) Baseline Inspection Report 05000348/2023010 and 05000364/2023010 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal ML23164A2182023-06-14014 June 2023 Draft Safety Evaluation for License Amendment Request to Revise Technical Specification 4.3, Fuel Storage, to Correct Tabulated Values from the Associated SFP Criticality Analysis (EPID L-2022-LLA-0138) - Letter NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 IR 05000348/20234402023-05-0505 May 2023 Reissue Farley Units-Final Significance Determination for a Security-Related Greater than Green Finding, Nov and Assessment Followup LTR, IR 05000348/2023440 and 05000364/2023440 - Cover IR 05000348/20230012023-05-0404 May 2023 Integrated Inspection Report 05000348/2023001 and 05000364/2023001 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 2024-01-30
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Inspection Report - Farley - 2011013 |
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UNITED STATES August 15, 2011
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, FINAL SIGNIFICANCE DETERMINATION OF A GREEN FINDING (NRC INSPECTION REPORT 05000348/2011013 AND 05000364/2011013)
The purpose of this letter is to provide you the final results of our significance determination of the preliminary White finding (i.e., a finding with low to moderate increased safety significance)
discussed in NRC Inspection Report No. 05000348/2011-012 and 05000364/2011-012, dated June 8, 2011 (ADAMS Accession # ML111590912). The Initiating Events Cornerstone inspection finding (identified as AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch) was assessed using the Significance Determination Process (SDP) and was preliminarily characterized as White. The finding involved the failure to maintain the configuration of the 1A reactor coolant pump (RCP) oil lift pump system in accordance with plant design and drawings. This resulted in an electrical short on November 10, 2010 that caused a small fire on the Unit 1 main control room (MCR) 1A RCP board handswitch. The fire was quickly identified by control room operators during an attempt to operate the RCP oil lift pump, and promptly extinguished by operators without the need for additional fire mitigation measures.
The finding affected both units due to the common control room. The finding was assigned a cross-cutting aspect in the Work Practices component of the Human Performance area in that personnel proceeded in the face of uncertainty or unexpected circumstances during preventative maintenance activities and did not properly preplan work activities for identified corrective maintenance. H.4(a)
At your request, a Regulatory Conference was held on July 12, 2011, to discuss your views on this issue. A meeting summary was issued on July 15, 2011, which included copies of the slide presentation made by Southern Nuclear Operating Company (SNC) (ADAMS Accession #
ML111960460). During the meeting, your staff described your assessment of the significance of the finding and the corrective actions taken to resolve it, including the root cause evaluation of the finding. SNC staff also discussed the circumstances surrounding the main control room fire and presented information, including handswitch testing, to support its contention that the fire should be considered a non-challenging fire per the subjective guidance of NUREG 6850, Fire PRA Methodology for Nuclear Power Plants. Additionally, your staff presented new information
SNC 2 to be considered in the final SDP analysis of the event. More specifically, SNC addressed the impact of the MCR ventilation on the decision to evacuate the MCR and the human performance reliability impact of performing safe shutdown activities in the event the MCR is evacuated.
The NRC evaluated the information you presented in the conference and determined the fire event, caused by the mis-wiring of the 1A RCP oil lift pump pressure switch, was still considered to be potentially challenging. The NRC concluded that if not suppressed, the fire could eventually lead to MCR evacuation. The basis for assuming the fire could be potentially challenging was the subjective classification criteria of NUREG-6850, Section C.3.3.2, including that this was a fire requiring active intervention to prevent spread and the possible heat release rates associated with a fire in this location, numerous cables could be in the zone of influence.
At the conference, SNC presented the results of handswitch testing, which was performed to understand whether the fire would self-extinguish and therefore limit the potential spread of the fire. The results of the tests did indicate that the types of electrical faults seen in the electrical short occurring November 10, 2010, tend to self-extinguish. The NRC determined that the test configuration and its results could provide limited perspective on the potential for MCR fire propagation. During the actual fire, an operator removed the light indication array which potentially changed the air flow and relative oxygen concentration at the fire location which was not done in the test configuration. Finally, there was not a definitive indication that could confirm operator intervention did not extinguish the fire. The information provided was not sufficient for the NRC to definitively conclude that the fire in the MCR would have self-extinguished.
Therefore, this fire was classified as Potentially Challenging for the purposes of evaluating this event via the SDP.
The NRC also evaluated new information presented by SNC regarding the impact of the MCR ventilation on the decision to evacuate the MCR. Based on this information, the NRC concluded that the ventilation would remain in operation throughout the fire. This reduces the number of fires from the family of heat release rates of single cable fires that would require control room evacuation. Additionally, the information indicates that some time delay is warranted in developing a single cable bundle fire which increases the time available to extinguish a fire before evacuation would be required. Based on the new information presented by SNC at the conference, the NRC concluded that a reduction in the frequency of fires requiring MCR evacuation, and a corresponding reduction in the probability of MCR abandonment, was warranted.
After considering the information you provided at the regulatory conference, the NRC has concluded that the finding is appropriately characterized as Green, a finding of very low safety significance. The NRC also has determined that the finding is a violation of Technical Specification 5.4.1 as discussed in inspection report 05000348/2011-012 and 05000364/2011-012. The circumstances surrounding the violation was described in detail that inspection report.
Because this violation was of very low safety significance and it was entered into the licensees corrective action program as CR 2010116613, this violation is being treated as an NCV, consistent with the Enforcement Policy. NCV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch.
SNC 3 For administrative purposes, this letter is issued as NRC Inspection Report No.
05000348/2011013 and 05000364/2011013. Accordingly, AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch are updated consistent with the regulatory positions described in this letter. Therefore: AV 05000348,364/2011012-01, Flame Detected on the 1A RCP Handswitch, is updated as NCV 05000348,364/2011012-01 with a safety significance of Green and cross-cutting aspect in the Work Practices component of the Human Performance area H.4(a).
The NRC has concluded that the information regarding the reason for the violation the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance was achieved is already adequately addressed on the docket in inspection report 05000348/2011-012 and 05000364/2011-012. Therefore, you are not required to respond to this letter unless the description therein does not accurately reflect your corrective actions or your position.
You have 30 calendar days from the date of this letter to appeal the staffs significance determination for the Green finding or the NCV. An appeal of the Green finding will be considered to have merit only if it meets the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2.
Additionally, if you disagree with the cross-cutting aspect assigned to the finding in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your disagreement, to the Regional Administrator, Region II, and the NRC Resident Inspector at the Joseph M. Farley Nuclear Plant.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, Enclosure 1, and your response (if you choose to provide one), will be made available electronically for public inspection in the NRC Public Document Room or from ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. However, because of the security-related information contained in Enclosure 2, and in accordance with 10 CFR 2.390, a copy of Enclosure 2 will not be available for public inspection. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction.
Sincerely,
/RA/
Richard P. Croteau, Director Division of Reactor Projects Docket No.: 50-348, 50-364 License No.: NPF-2, NPF-8 cc: (See page 4)
___ML112270513__
OFFICE RII:DRP RII:DRP RII:DRP RII:DRS RII:EICS RII:DRP SIGNATURE Via email Via email Via email Via telecom SES /RA/ SMS /RA/
NAME TLighty ECrowe JSowa WRogers SSparks SShaeffer DATE 08/15/2011 08/15/2011 08/15/2011 08/11/2011 08/15/2011 0815/2011 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO
SNC 4 cc w/encl:
B. D. McKinney, Jr. J. L. Pemberton Regulatory Response Manager SVP & General Counsel-Ops & SNC Southern Nuclear Operating Company, Inc. Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution Electronic Mail Distribution M. J. Ajluni Chris Clark Nuclear Licensing Director Commissioner Southern Nuclear Operating Company, Inc. Georgia Department of Natural Resources Electronic Mail Distribution Electronic Mail Distribution T. D. Honeycutt John G. Horn Regulatory Response Supervisor Site Support Manager Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant Electronic Mail Distribution Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution Todd L. Youngblood Plant Manager Ted V. Jackson Joseph M. Farley Nuclear Plant Emergency Response and Radiation Electronic Mail Distribution Program Manager Environmental Protection Division L. P. Hill Georgia Department of Natural Resources Licensing Supervisor Electronic Mail Distribution Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution Tom W. Pelham Performance Improvement Supervisor Jeffrey T. Gasser Joseph M. Farley Nuclear Plant Chief Nuclear Officer Southern Nuclear Operating Company, Inc.
Southern Nuclear Operating Company, Inc. Electronic Mail Distribution Electronic Mail Distribution Cynthia A. Sanders R. L. Gladney Radioactive Materials Program Manager Licensing Engineer Environmental Protection Division Southern Nuclear Operating Company, Inc. Georgia Department of Natural Resources Electronic Mail Distribution Electronic Mail Distribution N. J. Stringfellow James C. Hardeman Licensing Manager Environmental Radiation Program Manager Southern Nuclear Operating Company, Inc. Environmental Protection Division Electronic Mail Distribution Georgia Department of Natural Resources Electronic Mail Distribution Paula Marino Vice President William D. Oldfield Engineering Principal Licensing Engineer Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant Electronic Mail Distribution Electronic Mail Distribution (cc continued next page)
SNC 5 (cc continued)
Mr. Mark Culver Chairman Houston County Commission P. O. Box 6406 Dothan, AL 36302 James A. Sommerville Program Coordination Branch Chief Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution James L. McNees, CHP Director Office of Radiation Control Alabama Dept. of Public Health P. O. Box 303017 Montgomery, AL 36130-3017 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 1552 P.O. Box 30317 Montgomery, AL 36130-3017 L. L. Crumpton Administrative Assistant, Sr.
Southern Nuclear Operating Company, Inc.
Electronic Mail Distribution F. Allen Barnes Director Environmental Protection Division Georgia Department of Natural Resources Electronic Mail Distribution
SNC 6 Letter to L. Michael Stinson from Richard P. Croteau dated August 15, 2011 SUBJECT: JOSEPH M. FARLEY NUCLEAR PLANT, FINAL SIGNIFICANCE DETERMINATION OF A GREEN FINDING (NRC INSPECTION REPORT 05000348/2011013 AND 05000364/2011013)
Distribution w/encl:
RidsNrrPMFarley Resource C. Evans, RII L. Douglas, RII OE Mail RIDSNRRDIRS PUBLIC