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Category:Letter
MONTHYEARML23304A1422024-02-0101 February 2024 Issuance of Environmental Scoping Summary Report Associated with the U.S. Nuclear Regulatory Commission Staffs 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) IR 05000269/20243012024-01-11011 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) ML23262A9672023-12-13013 December 2023 Alternative to Use RR-22-0174, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section XI, Division 1 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 ML23317A3462023-11-14014 November 2023 Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 ML23219A1402023-10-10010 October 2023 Audit Report Proposed Alternative to Use ASME Code Case N-752, Risk Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems XI, Division 1 ML23269A1102023-10-0606 October 2023 Letter to Steven Snider-Revised Schedule for the Environmental Review of the Oconee Nuclear Station, Unit 1, 2, and 3, Subsequent License Renewal Application ML23256A0882023-09-25025 September 2023 Issuance of Alternative to Steam Generator Welds ML23195A0782023-08-29029 August 2023 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1 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 ML23208A0972023-07-27027 July 2023 Subsequent License Renewal List of Threatened and Endangered Species That May Occur in Your Proposed Project Location or May Be Affected 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 ML23178A0682023-07-0303 July 2023 Audit Plan Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 & 3 Systems Section XI, Division 1 ML23132A2392023-06-0101 June 2023 Summary of the April 2023 Remote Environmental Audit Related to the Review of the Subsequent License Renewal Application ML23144A0192023-05-25025 May 2023 Review of the Spring 2022 Steam Generator Tube Inspection Report (O3R31) IR 05000269/20230012023-05-12012 May 2023 Integrated Inspection Report 05000269/2023001 and 05000270/2023001 and 05000287/2023001 ML23121A0552023-05-0303 May 2023 Acknowledgement of Withdrawal Request to Revise TS 5.5.2 Containment Leakage Rate Testing Program ML23118A0762023-05-0101 May 2023 Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI ML23117A0432023-04-20020 April 2023 Framatome, Inc., Part 21 Notification of Existence of a Defect ML23075A0732023-04-0505 April 2023 License Renewal Regulatory Audit Regarding the Environmental Review of the Subsequent License Renewal Application Supplement (EPID Number L-2021-SLE-0002) ML23045A1432023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - State Tribe Letter ML23045A1402023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Shpo Letter ML23045A1332023-03-15015 March 2023 Request for Scoping Comments Concerning the Supplemental Environmental Review of Oconee Nuclear Station, Units 1, 2, and 3, Subsequent License Renewal Application - Achp Letter ML22332A4932023-03-10010 March 2023 William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility ML23069A1102023-03-10010 March 2023 Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection ML23061A1772023-03-0303 March 2023 Notification of Oconee Nuclear Station Comprehensive Engineering Team Inspection - NRC Inspection Report 05000269/2023011, 05000270/2023011 and 05000287/2023011 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) ML23039A1632023-02-0808 February 2023 Requalification Program Inspection ML23033A3472023-02-0606 February 2023 Letter - Revision No. 14 of Certificate of Compliance No. 9319, for the Model Nos. MAP-12 and MAP-13 Transportation Packages 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 ML22363A3942023-01-12012 January 2023 Subsequent License Renewal Environmental Report Supplement - Proposed Review Schedule ML22356A0512022-12-14014 December 2022 Curtiss-Wright Nuclear Division, Letter Regarding Potential Efect in a Configuration of the 11/2 Inch Quick Disconnect Connector Cable Assemblies Supplied to Duke Energy (See Attached Spreadsheet) for a Total of 460 of Connectors Only Suppl ML22321A0492022-12-0808 December 2022 Issuance of Amendment Nos. 426, 428 and 427, Additional Mode Change Limitations Applicable to the Adoption of TSTF- 359, Revision 9, Increase Flexibility in Mode Restraints ML22329A1042022-11-29029 November 2022 Review of the Fall 2021 Steam Generator Tube Inspection Report ML22321A1582022-11-22022 November 2022 Summary of Conference Call Regarding the Fall 2022 Steam Generator Tube Inspections ML22096A0032022-11-18018 November 2022 McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations ML22256A2532022-11-14014 November 2022 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2 IR 05000269/20220032022-11-0707 November 2022 Integrated Inspection Station 05000269/2022003 and 05000270/2022003 and 05000287/2022003 ML22301A0112022-11-0303 November 2022 Request for Withholding Information from Public Disclosure Regarding the SLR Application - September 2, 2022 ML22298A0752022-10-27027 October 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application Duke Energy Letter Dated July 25, 2022 ML22264A0322022-10-20020 October 2022 _Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application - Duke Energy Letter Dated July 8, 2022 IR 05000269/20220112022-09-26026 September 2022 NRC Inspection Report 05000269/2022011 and 05000270/2022011 and 05000287/2022011 ML22258A0302022-09-15015 September 2022 Evacuation Time Estimate Reports ML22222A0072022-09-14014 September 2022 Request for Withholding Information from Public Disclosure Regarding the Subsequent License Renewal Application 2024-02-01
[Table view] Category:Licensee Event Report (LER)
MONTHYEAR05000287/LER-2017-0012017-09-20020 September 2017 Unit 3 Reactor Protection System Actuation - Reactor Trip due to Turbine Trip from Generator Lockout, LER 17-001-00 for Oconee Nuclear Station, Unit 3, Regarding Reactor Protection System Actuation - Reactor Trip due to Turbine Trip from Generator Lockout 05000287/LER-2016-0012016-08-26026 August 2016 1 of 3, LER 16-001-00 for Oconee, Unit 3, Regarding Reactor Building Cooling Unit Inoperability Exceeds Technical Specification Completion Time 05000269/LER-2016-0012016-05-0505 May 2016 1 of 3, LER 16-001-00 for Oconee Nuclear Station, Unit 1, Regarding RPS Actuation - Unit 1 Reactor Trip Initiated by a Generator Lockout/Turbine Trip ML11364A0462011-12-23023 December 2011 Special Report Per Technical Specification 5.6.6, Problem Investigation Process Nos.: 0-11-13855, 0-11-14092 ML12006A1922011-12-19019 December 2011 LER 11-03-001 for Oconee, Units 1, 2, and 3 Regarding Inoperability of the Standby Shutdown Facility Diesel Generator ML0932902002009-11-18018 November 2009 10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance USA/9319/B(U)F-96, Revision, for the Model No. MAP-12/MAP-13 Package ML0534104592005-12-0101 December 2005 Special Report Per Selected Licensee Commitment 16.9.9, Problem Investigation Process No.: O-05-7215 for Oconee Regarding the Inoperability of the Station Auxiliary Service Water (Asw) System and the Stand-by Shutdown Facility (Ssf) Asw Sys ML0426503832004-09-0909 September 2004 LER 04-02-001 for Oconee Nuclear Station Re Main Steam Line Break Mitigation Design/Analysis Deficiency ML0313204452003-04-24024 April 2003 LER 03-S01-00 for Oconee, Units 1, 2 & 3 Re Security Access Revoked for Falsification of Criminal Record ML0232303392002-11-12012 November 2002 LER 02-S02-00 for Oconee Nuclear Station Regarding Uncontrolled Safeguards Information ML0215802872002-05-28028 May 2002 LER 2002-02-00 Re Potential for Fire to Indirectly Damage Mitigation Component for Oconee Nuclear Station Unit 1 ML0211201432002-04-0909 April 2002 LER 02-01-00 for Oconee Nuclear Station Unit 1 Re Security Access Revoked for Falsification of Criminal Record 2017-09-20
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AR E VA CERTIFIED MAIL SEM-09-014 RETURN RECEIPT REQUESTED November 18, 2009 U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk Director, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, Washington, DC 20555-0001
Subject:
10 CFR 71.95 Report of Non-Compliance with Certificate of Compliance USAI9319/B(U)F-96, Revision, for the Model No. MAP-1 2IMAP-13 Package To Whom It May Concern, On September 29, 2009, AREVA NP Inc. discovered that a single MAP-12 shipping container containing two fuel assemblies, transported from our facility located in Lynchburg, Virginia to the Oconee Nuclear Station located in Oconee, South Carolina violated the requirements of NRC Certificate of Compliance (CoC) USA/9319/B(U)F-96, Revision 2, Section 5(a) (3), in that not all of the requirements of section 2.3.4 Positive Closure in the Safety Analysis Report (SAR) were met.
Specifically, a pin did not fully engage resulting in the dislodgement during transit to the Oconee site.
The current procedure for pin insertion may not allow the pin to be fully engaged resulting in the potential to become dislodged during transit. Section 2.3.4 of the SAR states that the lid is secured to the base using numerous ball lock pins (44 for MAP-12). Based on this incident, AREVA has updated their procedures to further ensure the proper engagement of the ball lock pin. Attachment A to this letter provides additional information related to this shipment.
Per 10 CFR 71.95 (a) (1), AREVA does not consider the conditions of the subject shipment, listed in this notice, to have caused a significant reduction in the effectiveness of the package. There was no impact to the safety basis of the package or increased risk to the public. This report is being made in accordance with the requirements of 10 CFR 71.95 (A) (3); Instances in which the conditions of approval in the Certificate of Compliance were not observed in making a shipment. Further justification is provided in Attachment A.
If you or your staff have any questions, require additional information, or wish to discuss the matter further, please contact me at 434-832-5205.
Sincerely, Samuel E. Miller Manager Environmental, Health Safety & Licensing AR EVA NP INC.-
An AREVA and Siemens company 3315 Old Forest Road, P.O. Box 10935. Lynchburg. VA 24506-0935 Tel.: (434) 832-3000 - Fax: (434) 832-3840 FoR: 22709VA-1 (411rAW)
i SEM-09-014 November 15, 2009 Cc:
E.W. Branch Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001 AREVA NP INC.
An AREVA and Siemens company 3315 Old Forest Road. P.O. Box 10935, Lynchburg. VA 24506-0935 Tel.: (434) 832-3000 - Fax: (434) 832-3840 FORM:
nlý' (.112OD5)
SEM-09-014 November 15, 2009 Attachment A Additional Information AREVA NP INC.
An AREVA and Siemens company 3315 Old Forest Road. P.O. Box 10935. Lynchburg, VA 24506-0935 Tel.: (434) 832-3000 - Fax: (434) 832-3840 FORM;WSV*t 14'I I(- )
SEM-09-014 November 15, 2009 10 CFR 71.95 Sections (1) and (2)
(1) A brief abstract describing the major occurrences during the event, including all component or system failures that contributed to the event and significant corrective action taken or planned to prevent recurrence.
On September 23, 2009, AREVA NP Inc. discovered that a single MAP-12 shipping container containing two fuel assemblies, transportedfrom our facility located in Lynchburg, Virginia to the Oconee Nuclear Station located in Oconee, South Carolina violated the requirements of NRC Certificate of Compliance (CoC) USA/9319/B(U)F-96, Revision 2, Section 5(a) (3), in that not all of the requirements of section 2.3.4 Positive Closure in the Safety Analysis Report (SAR) were met.
Specifically, a pin did not fully engage resulting in the dislodgement during transit at the Oconee site.
There were no component or system failures during the event.
An inspection of package MP-066 indicated that the package was preparedproperly according to procedures and that the ball lock pin might have become lodged in the hole and not fully seated.
Without being fully seated the ball lock pin could not properly engage thus allowing it to possibly becoming dislodged during transit.
To prevent a recurrence of this error, AREVA has updated procedures to have an independent reviewer to go behind and insure that the ball lock pins have engaged properly with each containerfor each shipment.
(2) A clear, specific, narrative description of the event that occurred so that knowledgeable readers conversant with the requirements of part 71, but not familiar with the design of the packaging,. can understand the complete event. The narrative description must include the following specific information as appropriate for the particular event.
(i) Status of components or systems that were inoperable at the start of the event and that contributed to the event; There was no inoperable component or system at the startof the event of that contributedto the event. The single MAP package containedtwo fuel assemblies. All safety requirements were met in preparationof the packaging for shipment with the exception of the one (1) noted ball lock pin that was missing on receipt of package MP-066 at the Oconee site.
(ii) Dates and approximate times of occurrences; A single shipment of six (6) MAP-12 packages, each containing two fuel assemblies, was loaded as a single conveyance and subsequently shipped on September 23, 2009. The shipment arrived at the Oconee site on September 24, 2009.
(iii) The cause of each component or system failure or personnel error, if known; There were no component or system failures. An issue evaluationidentified no independent verification of the ball lock pin full engagement was performed because the procedure did not specify as a requiredprocess.
AREVANP INC.
An AREVA and Siomons company 3315 Old Forest Road. P.O. Box 10935, Lynchburg, VA 24506-0935 Tel.: (434) 832-3000 - Fax: (434) 832-3840 FOR; 22709w*l(rWoM)
SEM-09-014 November 15, 2009 (iv) The failure mode, mechanism, and effect of each failed component, if known; There were no failed components.
(v) A list of systems or secondary functions that were also affected for failures of components with multiple functions; There were no other systems or secondaryfunctions that were affected by the missing ball lock pin.
(vi) The method of discovery of each component or system failure or procedural error; There were no component or system failures. The missing ball lock pin was discovered on package MP-066 by Hittman Transport (Kelly Sievert) priorto arriving at the Oconee site and he notified Oconee Nuclear Station upon arrival.
(vii) For each human performance-related root cause, a discussion of the cause(s) and circumstances; The procedure was not sufficient to prevent dislodgement of ball lock pin. AREVA did not recognize the deficiency of the procedure until this occurrenceinvestigation was performed.
(viii) The manufacturer and model number (or other identification) of each component that failed during the event; and There were no component failures during the event.
(ix) For events occurring during use of packaging, the quantities and chemical and physical form(s) of the package contents.
The shipment involved six (6) MAP-12 packages containing two (2) fuel assemblies. Each fuel assembly consists of uranium dioxide pellets clad in zirconium alloy tubing and arrangedin a lattice with installationin a cage or structure. The materialis solid normal form. The enrichments were all less than 5.0 wt% 235U. Only the single MAP-12 package MP-066 was noted to have a missing ball lock closure pin.
AREVA NP jNC.
An AREVA and Siemens company 3315 Old Forest Road. P.O. Box 10935. Lynchburg. VA 24506-0935 Tel.: (434) 832-3000 - Fax: (434) 832-3840 FOR. 227gv0.9Vt
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