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Category:Letter
MONTHYEAR05000270/LER-2024-001, Common Cause Inoperability of Both Trains of Control Room Ventilation System Outside Air Booster Fans Due to Supply Breaker Wiring Deficiency Resulted in a Condition That Have Prevented Fulfillment2024-12-19019 December 2024 Common Cause Inoperability of Both Trains of Control Room Ventilation System Outside Air Booster Fans Due to Supply Breaker Wiring Deficiency Resulted in a Condition That Have Prevented Fulfillment. 05000269/LER-2024-001, Standby Shutdown Facility (Ssf) Pressurizer Level Switch Configuration Caused by Legacy Procedure Deficiency Resulted in Condition Prohibited by Technical Specifications2024-12-19019 December 2024 Standby Shutdown Facility (Ssf) Pressurizer Level Switch Configuration Caused by Legacy Procedure Deficiency Resulted in Condition Prohibited by Technical Specifications 05000269/LER-2022-001-01, Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure Boundary2024-11-0707 November 2024 Ultrasonic Examination Indication Identifies Degraded Reactor Coolant System Pressure Boundary ML24305A1492024-11-0404 November 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report (O2R31) IR 05000269/20240032024-10-31031 October 2024 Integrated Inspection Report 05000269/2024003 and 05000270/2024003 and 05000287/2024003 (2) ML24255A3322024-10-16016 October 2024 SLRA - Revised SE Letter ML24297A6172024-10-11011 October 2024 PCA Letter to NRC Oconee Hurricane Helene ML24269A0912024-10-0909 October 2024 Request for Withholding Information from Public Disclosure IR 05000269/20243012024-09-23023 September 2024 NRC Operator License Examination Report 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML24145A1782024-08-26026 August 2024 Issuance of Amendment Nos. 430, 432, and 431, to TS 5.5.2, Containment Leakage Rate Testing Program for a one-time Extension of the Type a Leak Rate Test Frequency IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) ML24220A1092024-08-0808 August 2024 – Operator Licensing Examination Approval 05000269/2024301, 05000270/2024301, and 05000287/2024301 05000287/LER-2024-001, Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation2024-08-0202 August 2024 Procedure Deficiency Results in Inadvertent Automatic Feedwater Isolation and Automatic Emergency Feedwater Actuation IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 ML24192A1312024-07-15015 July 2024 Licensed Operator Positive Fitness-For-Duty Test ML24183A0972024-07-12012 July 2024 ISFSI; Catawba 1, 2 & ISFSI; McGuire 1, 2 & ISFSI; Oconee 1, 2, 3 & ISFSI; Shearon Harris 1; H. B. Robinson 2 & ISFSI; and Radioactive Package Shipping Under 10 CFR 71 (71-266 & 71-345) – Review of QA Program Changes EPID L-2024-LLQ-0002 ML24183A2352024-06-29029 June 2024 Update 3 to Interim Report Regarding a Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 ML24179A1102024-06-27027 June 2024 Submittal of Updated Final Safety Analysis Report Revision 30, Technical Specifications Bases Revisions, Selected Licensee Commitment Revisions, 10 CFR 50.59 Evaluation Summary Report, and 10 CFR 54.37 Update, and Notification ML24141A0482024-05-17017 May 2024 EN 56958_1 Ametek Solidstate Controls, Inc IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 ML24108A0792024-04-16016 April 2024 EN 57079 Paragon Energy Solutions Email Forwarding Part 21 Interim Report Re Potential Defect with Schneider Electric Medium Voltage Vr Type Circuit Breaker Part Number V5D4133Y000 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 ML24088A3052024-03-25025 March 2024 Fws to NRC, Agreement with Nlaa Determination for Tricolored Bat for Oconee Lr 05000287/LER-2023-002, Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications2024-02-29029 February 2024 Passive Containment Isolation Device Inoperability Results in Operation or Condition Prohibited by Technical Specifications 05000270/LER-2023-001, Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee2024-02-29029 February 2024 Inappropriate Procedural Guidance for Planned Online Maintenance Results in Event or Condition That Could Have Prevented Fulfillment of a Safety Function Licensee IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) ML24045A3072024-02-16016 February 2024 Ltr. to Pete Parr Chief Pee Dee Indian Tribe Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24030A0052024-02-16016 February 2024 Ltr. to Brian Harris, Chief, Catawba Indian Nation; Re., Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2992024-02-16016 February 2024 Ltr. to Eric Pratt Chief the Santee Indian Organization Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3082024-02-16016 February 2024 Ltr. to Ralph Oxendine Chief Sumter Tribe of Cheraw Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3032024-02-16016 February 2024 Ltr. to John Creel Chief Edisto Natchez-Kusso Tribe of Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2952024-02-16016 February 2024 Ltr. to Chuck Hoskin, Jr, Principal Chief Cherokee Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3062024-02-16016 February 2024 Ltr. to Michell Hicks, Principal Chief Eastern Band of Cherokee Re Oconee Nuclear Station Units 1,2, and 3 Section 106 ML24045A3012024-02-16016 February 2024 Ltr. to Harold Hatcher Chief the Waccamaw Indian People Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2972024-02-16016 February 2024 Ltr. to Dexter Sharp Chief Piedmont American Indian Assoc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3022024-02-16016 February 2024 Ltr. to Joe Bunch United Keetoowah Band of Cherokee Indians in Ok Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2962024-02-16016 February 2024 Ltr. to David Hill Principal Chief Muscogee Creek Nation Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A2942024-02-16016 February 2024 Ltr. to Carolyn Chavis Bolton Chief Pee Dee Indian Nation of Upper Sc Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3042024-02-16016 February 2024 Ltr. to Lisa M. Collins Chief the Wassamasaw Tribe of Varnertown Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24045A3052024-02-16016 February 2024 Ltr. to Louis Chavis Chief Beaver Creek Indians Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 ML24011A1482024-02-13013 February 2024 Letter to Steven M. Snider-Oconee Nuclear Sta, Unites 1,2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML24030A5212024-02-13013 February 2024 Letter to Elizabeth Johnson, Director, SHPO; Re Oconee Nuclear Stations Units 1, 2, and 3 Section 106 ML24019A1442024-02-13013 February 2024 Letter to Reid Nelson, Executive Director, Achp; Re Oconee Nuclear Station Units 1, 2, and 3 Section 106 IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24011A1532024-02-13013 February 2024 Letter to Tracy Watson EPA-Oconee Nuclear Sta, Unites 1, 2 & 3 Notice of Avail of the Draft Site-Specific Supp. 2, 2nd Renewal to the Generic EIS for Lic. Renew of Nuclear Plants ML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staff’S Review of the Oconee Nuclear Station, Units 1, 2, & 3, Subsequent License Renewal Application ML24005A2492024-01-24024 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting) ML24017A0582024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 2024-09-23
[Table view] Category:Notice of Violation
MONTHYEARIA-24-023, Notice of Violation2025-01-31031 January 2025 Notice of Violation IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation IR 05000269/20140122014-08-12012 August 2014 EA-14-091 Oconee Nuclear Station - Final Significance Determination of White Finding, Notice of Violation and Assessment Follow-Up Letter (NRC Inspection Report No. 05000269/2014012) ML13114A9282013-07-0101 July 2013 Notice of Violation and Confirmatory Order Related to a Fire Protection Program License Condition IR 05000269/20110192011-12-0606 December 2011 Final Significance Determination of One Yellow Finding and One Green Finding and Notice of Violation (NRC Inspection Report 05000269/2011019, 05000270/2011019, and 05000287/2011019 - Oconee Nuclear Station) ML1106107392011-02-24024 February 2011 Information Related to the Safety Significance of the Apparent Violation Concerning Failure of Unit 1 Residual Heat Removal System Low Pressure Injection Valve IR 05000269/20100082010-08-12012 August 2010 Final Significance Determination of One Yellow Finding and One White Finding and Notice of Violation (NRC Inspection Report 05000269-10-008, 05000270-10-008, and 05000287-10-008 - Oconee Nuclear Station) ML0704500212007-02-13013 February 2007 Final Significance Determination for a White Finding & NOV IR 05000269/20060172006-11-22022 November 2006 (Redacted)Ir 05000269-06-017, IR 05000270-06-017, and IR 05000287-06-017, Final Significance Determination for a White Finding and Notice of Violation, Duke Energy Carolinas, LLC IR 05000269/20060152006-07-31031 July 2006 Final Significance Determination for Greater than Green Finding and Notice of Violation; IR 05000269-06-015, 05000270-06-015, and 05000287-06-015 IR 05000269/20040132004-09-24024 September 2004 EA-04-115 - Final Significance Determination for a White Finding and Notice of Violation (NRC Inspection Report 05000269, 270, 287/2004013, Oconee Nuclear Station IR 05000269/20030072003-02-0707 February 2003 IR 05000269-03-007, IR 05000270-03-007 & IR 05000287-03-007, on 11/21/2002, Oconee Nuclear Station(Seneca, Sc) Final Significance Determination for a White Finding and Notice of Violation ML0221406722002-08-0202 August 2002 EA-02-048 - Final Significance Determination for White Finding & NOV IR 05000269/20020112002-07-26026 July 2002 IR 05000269-02-011, IR 05000270-02-011, & IR 05000287-02-011, NOV & Final Significance Determination 2025-01-31
[Table view] Category:Inspection Report
MONTHYEARML24305A1492024-11-0404 November 2024 Review of the Fall 2023 Steam Generator Tube Inspection Report (O2R31) IR 05000269/20240032024-10-31031 October 2024 Integrated Inspection Report 05000269/2024003 and 05000270/2024003 and 05000287/2024003 (2) IR 05000269/20243012024-09-23023 September 2024 NRC Operator License Examination Report 05000269/2024301, 05000270/2024301, and 05000287/2024301 IR 05000269/20240052024-08-26026 August 2024 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 (Report 05000269/2024005, 05000270/2024005, and 05000287-2024005) IR 05000269/20240102024-08-0101 August 2024 Focused Engineering Inspection - Age-Related Degradation Report 05000269/2024010 and 05000270/2024010 and 05000287/2024010 IR 05000269/20240022024-07-25025 July 2024 Integrated Inspection Report 05000269/2024002 and 05000270/2024002 and 05000287/2024002 IR 05000269/20240012024-05-0303 May 2024 Integrated Inspection Report 05000269/2024001, 05000270/2024001 and 05000287/2024001 IR 05000269/20244022024-04-24024 April 2024 Security Baseline Inspection Report 05000269/2024402 and 05000270/2024402 and 05000287/2024402 IR 05000269/20244012024-03-28028 March 2024 – Security Baseline Inspection Report 05000269-2024401 and 05000270-2024401 and 05000287-2024401 IR 05000269/20230062024-02-28028 February 2024 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2 and 3 - (NRC Inspection Report 05000269/2023006, 05000270/2023006, and 05000287/2023006) IR 05000269/20230042024-02-13013 February 2024 Integrated Inspection Report 05000269/2023004, 05000270/2023004, and 05000287/2023004; and Inspection Report 07200040/2023001 ML24017A0582024-01-11011 January 2024 Notification of Licensed Operator Initial Examination 05000269/2024301, 05000270/2024301, and 05000287/2024301 ML23331A7982023-12-14014 December 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report (01R32) IR 05000269/20230032023-11-14014 November 2023 Integrated Inspection Report 05000269/2023003, 05000270/2023003, and 05000287/2023003; and IR 07200040/2023001; and Exercise of Enforcement Discretion IR 05000269/20230052023-08-25025 August 2023 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2 and 3 (Report 05000269/2023005, 05000270/2023005, and 05000287/2023005) IR 05000269/20230112023-08-25025 August 2023 Comprehensive Engineering Team Inspection Report 05000269/2023011 and 05000270/2023011 and 05000287/2023011 IR 05000269/20230022023-07-28028 July 2023 Integrated Inspection Report 05000269/2023002, 05000270/2023002 and 05000287/2023002 IR 05000269/20230102023-07-19019 July 2023 Biennial Problem Identification and Resolution Inspection Report 05000269/2023010 and 05000270/2023010 and 05000287/2023010 and Notice of Violation ML23124A0302023-05-18018 May 2023 Security Baseline Inspection Report 05000269/2023420 and 05000270/2023420 and 05000287/2023420 RA-23-0128, Refuel 32 (O1R32) Steam Generator Tube Inspection Report2023-05-18018 May 2023 Refuel 32 (O1R32) Steam Generator Tube Inspection Report IR 05000269/20234202023-05-18018 May 2023 Security Baseline Inspection Report 05000269/2023420 and 05000270/2023420 and 05000287/2023420 IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 IR 05000269/20234012023-04-14014 April 2023 – Security Baseline Inspection Report 05000269 2023401 and 05000270 2023401 and 05000287 2023401 IR 05000269/20220062023-03-0101 March 2023 Annual Assessment Letter for Oconee Nuclear Nuclear Station, Units 1, 2 and 3 (NRC Inspection Report 05000269/2022006, 05000270/2022006, and 05000287/2022006) ML23037A0772023-02-0606 February 2023 402 Cyber Notification and RFI Letter Final IR 05000269/20220042023-02-0202 February 2023 Integrated Inspection Report 05000269 2022004 and 05000270/2022004 and 05000287/2022004 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 IR 05000269/20224012022-08-26026 August 2022 Material Control and Accounting Program Inspection Report 05000269/2022401 and 05000270/2022401 and 05000287/2022401 (OUO Removed) IR 05000269/20220052022-08-26026 August 2022 Updated Inspection Plan for Oconee Nuclear Station, Units 1, 2 and 3 - NRC Inspection Report 05000269/2022005, 05000270/2022005, and 05000287/2022005 IR 05000270/20220022022-07-29029 July 2022 Integrated Inspection Report 05000269/ 2022002 and 05000270/2022002 and 05000287/2022002 IR 05000269/20220102022-06-30030 June 2022 Triennial Fire Protection Inspection Report 05000269/2022010 and 05000270/2022010 and 05000287/2022010 IR 05000269/20220012022-05-0404 May 2022 Integrated Inspection Report 05000269/2022001, 05000270/2022001 and 05000287/2022001 IR 05000269/20224032022-05-0404 May 2022 Security Baseline Target Set Inspection Report 05000269/2022403 and 05000270/2022403 and 05000287/2022403 IR 05000269/20224042022-04-27027 April 2022 Security Baseline Inspection Report 05000269/2022404 and 05000270/2022404 and 05000287/2022404 IR 05000269/20223012022-03-0707 March 2022 Notification of Licensed Operator Initial Examination 05000269/2022301, 05000270/2022301 and 05000287/2022301 IR 05000269/20210062022-03-0202 March 2022 Annual Assessment Letter for Oconee Nuclear Station, Units 1, 2, and 3 (Report 05000269/2021006, 05000270/2021006, and 05000287/2021006) IR 05000269/20220122022-02-24024 February 2022 Safety Conscious Work Environment Issue of Concern Followup Report 05000269/2022012 and 05000270/2022012 and 05000287/2022012 IR 05000269/20224022022-02-16016 February 2022 Security Baseline Inspection Report 05000269/2022402 and 05000270/2022402 and 05000287/2022402 IR 05000269/20210042022-02-14014 February 2022 Integrated Inspection Report 05000269/2021004 and 05000270/2021004 and 05000287/2021004 and Apparent Violation IR 05000269/20210032021-10-28028 October 2021 Integrated Inspection Report 05000269/2021003 and 05000270/2021003 and 05000287/2021003 IR 05000269/20210102021-09-17017 September 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000269/2021010 and 05000270/2021010 and 05000287/2021010 IR 05000269/20210052021-08-26026 August 2021 Updated Inspection Plan for Oconee Nuclear Station Units 1, 2, and 3 (NRC Inspection Report 05000269/2021005, 05000270/2021005, and 05000287/2021005) IR 07200004/20210012021-08-26026 August 2021 Operation of an Independent Spent Fuel Storage Installation Report 07200004/2021001 IR 05000269/20210022021-08-0404 August 2021 Integrated Inspection Report 05000269/2021002 and 05000270/2021002 and 05000287/2021002 IR 05000269/20213012021-07-0606 July 2021 NRC Operator License Examination Report 05000269/2021301, 05000270/2021301, and 05000287/2021301 IR 05000269/20210112021-06-0202 June 2021 Biennial Problem Identification and Resolution Inspection Report 05000269/2021011 and 05000270/2021011 and 05000287/2021011 IR 05000269/20210012021-04-23023 April 2021 Integrated Inspection Report 05000269/2021001 and 05000270/2021001 and 05000287/2021001 IR 05000269/20214012021-04-22022 April 2021 Security Baseline Inspection Report 05000269/2021401, 05000270/2021401 and 05000287/2021401 (U) IR 05000269/20200062021-03-0303 March 2021 Annual Assessment Letter for Oconee Nuclear Station Units 1, 2, & 3 NRC Inspection Report 05000269/2020006, 05000270/2020006, & 05000287/2020006 2024-09-23
[Table view] |
Inspection Report - Oconee - 2006017 |
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Text
November 22, 2006
SUBJECT:
FINAL SIGNIFICANCE DETERMINATION FOR A WHITE FINDING AND NOTICE OF VIOLATION (OCONEE NUCLEAR STATION - NRC INSPECTION REPORT NOS. 05000269/2006017, 05000270/2006017, AND 05000287/2006017)
Dear Mr. Hamilton:
The purpose of this letter is to provide you with the Nuclear Regulatory Commissions (NRC)
final significance determination for a finding involving the failure of Dukes Oconee Nuclear Station to effectively control maintenance activities, and also the failure to assess and manage the risk, associated with removing an access cover in the south wall of the standby shutdown facility (SSF) to facilitate installation of temporary electrical power cables.
The finding was initially documented in NRC Integrated Inspection Report Nos.
05000269,270,287/2006002, which was issued on April 28, 2006. NRC Inspection Report Nos.
05000269,20,287/2006016, dated August 31, 2006, documented the NRCs assessment of the finding under the significance determination process, and concluded that the finding was a preliminary White issue (i.e., an issue of low to moderate safety significance which may require additional NRC inspection). The cover letter to our inspection report of August 31st provided Duke an opportunity to request a regulatory conference on this matter. In lieu of a regulatory conference, Duke chose to provide a written response, dated October 5, 2006.
Dukes written response documented its conclusion that a performance deficiency did not exist as described in the NRCs inspection report of August 31, 2006. Additionally, based on its review, Duke concluded that the NRCs SDP Phase 3 evaluation, the conclusions of which are inappropriately based on qualitative factors resulting in the preliminary White finding, support a conclusion that the resulting safety significance was actually very low (Green).
After carefully considering the information developed during the inspection and the information provided in Dukes written response, the NRC has concluded that the final inspection finding is appropriately characterized as White in the Mitigating Systems cornerstone. In response to Dukes contention that the matter does not represent a performance deficiency, the NRC notes that although the access penetration may have been constructed in 1992 to the best estimate of flood height (4.71 feet above grade) at the time, by 1993 Duke was aware that this estimate was flawed and non-conservative. By 1993, Duke was aware that predicted flood heights were much higher than 4.71 feet. In fact, the percentage of floods that were assumed to overtop the effective five foot flood barrier/wall and fail the SSF was estimated to be 20 percent. As such,
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removal of the access cover would directly impact the accredited effectiveness of the five foot flood barrier/wall. In 1999, a Duke maintenance rule expert panel re-assessed the safety significance of the SSF flood barrier and concluded that the safety significance was low. The panel considered the SSF wall as a passive feature with the only likely failure being a watertight doorway. However, the panel failed to recognize that the access cover was susceptible to maintenance which could create a bypass around the wall and degrade the function of the wall.
Accordingly, since Dukes expert panel failed to act in consideration of the best available information at the time, the NRC considers the 1999 re-assessment of the SSF flood barrier to be non-conservative. Therefore, the staff concluded that Dukes subsequent failure to assess and manage the increased risk due to potential flooding that resulted from the SSF maintenance activity was a performance deficiency.
The NRC reviewed the information provided in Dukes written response, and concluded that changes to our preliminary analysis were warranted. In particular, the physical location of the SSF cover was revised to reflect the information provided by Duke. The NRC also agreed with Duke that an additional SSF success term (used in the staffs preliminary seismic evaluation)
was redundant, and as such this term was deleted from the final analysis. The staff did not agree, however, with Dukes recommended change to the initial fragility term (for seismic considerations), as no new information was provided by Duke to support such a change.
Applying these modifications to the final significance determination resulted in a change in core damage frequency that was consistent with the licensees assessment.
Duke also stated that, given the uncertainty associated with the results of an external events analysis, a qualitative assessment was more appropriate. The NRC recognized that such consideration was appropriate in this situation, and considered other attributes that would have a bearing on safety significance. These included defense in depth and the ability to protect the public given an accident. The initiating events associated with this performance deficiency fall into the rare occurrence category. However, for these postulated accident sequences, there was an exclusive reliance upon the SSF to prevent core damage (no redundancy or diversity of mitigation). Any functional degradation of the SSF flood barrier from these initiating events directly increased the failure probability of the SSF and therefore, increased the likelihood of core damage. With a loss of core cooling, the fuel cladding and the Reactor Coolant System would eventually fail, causing a loss of multiple barriers that protect the public. The significance of the SSF flood barrier was clearly understood and delineated in Dukes Probabilistic Risk Assessment for External Events, dated December 1996. Given the nature of the initiating events associated with this performance deficiency, the emergency plan response would also be impaired. Consequently, from a blended qualitative and quantitative perspective the NRCs final Significance Determination remains low to moderate (White).
You have 30 calendar days from the date of this letter to appeal the staffs determination of significance for the identified finding. Such appeals will be considered to have merit only if they meet the criteria given in NRC Inspection Manual Chapter 0609, Attachment 2.
The NRC also has determined that this finding resulted in a violation of regulatory requirements. In this case, the failure to use adequate procedures to control maintenance activities that could affect safety-related equipment was determined to be a violation of Technical Specification 5.4.1. As a result, Duke failed to assess and manage the increase in risk from external floods for this maintenance activity, as required by 10 CFR 50.65(a)(4). The violation is cited in the enclosed Notice of Violation (Notice), and the circumstances surrounding
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the violation are described in detail in NRC Inspection Report Nos. 05000269,270,287/2006016, dated August 31, 2006, and NRC Integrated Inspection Report Nos. 05000269,270,287/2006002, dated April 28, 2006. In accordance with the NRC Enforcement Policy, the Notice of Violation is considered escalated enforcement action because it is associated with a White finding.
You are required to respond to this letter and should follow the instructions specified in the enclosed Notice when preparing your response. The NRC will use your response, in part, to determine whether further enforcement action is necessary to ensure compliance with regulatory requirements.
For administrative purposes, this letter is issued as a separate NRC Inspection Report, No. 05000269,270,287/2006017, and the above violation is identified as VIO 05000269,270,287/2006017-01, White Finding - Inadequate Procedural Controls and Risk Management Associated with Breach in SSF Flood Protection Barrier. Accordingly, apparent violations AV 05000269,270,287/2006016-01 and AV 05000269,270,287/2006016-02 are closed.
Because plant performance for this issue has been determined to be in the regulatory response band, we will use the NRC Action Matrix to determine the most appropriate NRC response for this event. We will notify you by separate correspondence of that determination.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS) which is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, any response should not include any personal privacy, proprietary, classified, or safeguards information so that it can be made available to the public without redaction. The NRC also includes significant enforcement actions on its Web site at www.nrc.gov; select What We Do, Enforcement, then Significant Enforcement Actions.
Should you have any questions regarding this letter, please contact Mr. James Moorman, Chief, Branch 1, Division of Reactor Projects, at (404) 562-4647.
Sincerely,
/RA/ by Victor McCree Acting for/
William D. Travers Regional Administrator Docket Nos.: 50-269, 50-270, 50-287 License Nos.: DPR-38, DPR-47, DPR-55 Enclosure: Notice of Violation cc w/encl: (See page 4)
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cc w/encl:
B. G. Davenport Compliance Manager (ONS)
Duke Energy Corporation Electronic Mail Distribution Lisa Vaughn Associate General Counsel Duke Energy Corporation 526 South Church Street Mail Code EC 07H Charlotte, NC 28202 Timika Shafeek-Horton Assistant General Counsel Duke Energy Corporation 526 South Church Street-EC07H Charlotte, NC 28202 David A. Repka Winston & Strawn LLP Electronic Mail Distribution Beverly Hall, Acting Director Division of Radiation Protection N. C. Department of Environmental Health & Natural Resources Electronic Mail Distribution Henry J. Porter, Assistant Director Div. of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution R. Mike Gandy Division of Radioactive Waste Mgmt.
S. C. Department of Health and Environmental Control Electronic Mail Distribution County Supervisor of Oconee County 415 S. Pine Street Walhalla, SC 29691-2145 Lyle Graber, LIS NUS Corporation Electronic Mail Distribution R. L. Gill, Jr., Manager Nuclear Regulatory Issues and Industry Affairs Duke Energy Corporation 526 S. Church Street Charlotte, NC 28201-0006 Charles Brinkman Director, Washington Operations Westinghouse Electric Company 12300 Twinbrook Parkway, Suite 330 Rockville, MD 20852
ML063260154 OFFICE RII:EICS RII:DRP RII:DRS RII:ORA NRR SIGNATURE CFE CAC WGR VMM NAME EVANS CCASTO WROGERS VMcCree DATE 11/02/2006 11/02/2006 11/03/2006 11/22/2006 E-MAIL COPY?
YES NO YES NO YES NO YES NO
Enclosure NOTICE OF VIOLATION Duke Power Company
Docket Nos. 50-269, 50-270, 50-287 Oconee Nuclear Station License Nos. DPR-38, DPR-47, DPR-55 Units 1, 2 and 3 EA-06-199 During an NRC inspection completed on August 31, 2006, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below:
Technical Specification 5.4.1 requires that written procedures shall be established implemented and maintained as recommended in Regulatory Guide 1.33, Revision 2, Appendix A, February 1978. Regulatory Guide 1.33, Section 9, Procedures for Performing Maintenance, requires that maintenance which can affect the performance of safety-related equipment should be properly preplanned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
10 CFR 50.65 (a)(4), Requirements for monitoring the Effectiveness of Maintenance at Nuclear Power Plants requires in part, that prior to performing maintenance activities, the licensee shall assess and manage the increase in risk that may result from the proposed maintenance activities.
Contrary to the above, on August 13, 2003, while performing planned maintenance involving the opening of a penetration in the Standby Shutdown Facility (SSF) exterior wall to route temporary electrical power cables, the licensee failed to use an adequate procedure to open and control a penetration through a passive flood protection barrier and route temporary power cables. Specifically, the procedure used, IP/0/A/3010/006, Cable Pulling Procedure, Revision 16, did not address the installation of temporary power cables, and did not address breaching and restoring a flood barrier. As a result, the licensee failed to assess and manage the increase in risk associated with the degradation of the flood protection capability of the SSFs exterior wall from August 13, 2003 to August 3, 2005.
This violation is associated with a White significance determination process finding for Units 1, 2 and 3 in the Mitigating Systems cornerstone.
Pursuant to the provisions of 10 CFR 2.201, Duke Power Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN:
Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice of Violation (Notice) within 30 days of the date of the letter transmitting this Notice. This reply should be clearly marked as a "Reply to a Notice of Violation; EA-06-199" and should include: (1) the reason for the violation or, if contested, the basis for disputing the violation or severity level; (2) the corrective steps that have been taken and the results achieved; (3) the corrective steps that will be taken to avoid further violations; and (4) the date when full compliance will be achieved. Your response may reference or include previously docketed correspondence if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken. Where good cause is shown,
Notice of Violation
consideration will be given to extending the response time.
If you contest this enforcement action, you should also provide a copy of your response, with the basis for your denial, to the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001.
Because your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs document system (ADAMS) accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html, to the extent possible it should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
In accordance with 10 CFR 19.11, you may be required to post this Notice within 2 working days.
Dated this 22nd day of November 2006