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Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 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 NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums 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 NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report 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 NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) 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-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) 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-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 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 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
[Table view] Category:Licensee Response to Notice of Violation
MONTHYEARNL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 ML23116A2482023-04-26026 April 2023 (Vegp), Unit 3 - Response to Apparent Violation in NRC Inspection Report 05200025/2022011: EA-22-081 NL-21-0887, Response to Apparent Violation Noted in Inspection Report 05000424/2021401 and 05000425/2021401, EA-21-0262021-10-19019 October 2021 Response to Apparent Violation Noted in Inspection Report 05000424/2021401 and 05000425/2021401, EA-21-026 ML21278A3542021-10-0505 October 2021 Enclosure 1: Smc Position and Additional Information for the Final Significance Determination for Apparent Violations in NRC Letter EA-21-109 NL-20-0484, Reply to a Notice of Violation; EA-19-112, Inspection Report 05000424/2019-003 and 05000425/2019-0032020-04-30030 April 2020 Reply to a Notice of Violation; EA-19-112, Inspection Report 05000424/2019-003 and 05000425/2019-003 NL-20-0037, Pre-decisional Reply to EA-19-112, NRC Inspection Report 05000424/2019090 and 05000425/2019090 and Preliminary White Finding and Apparent Violation2020-01-31031 January 2020 Pre-decisional Reply to EA-19-112, NRC Inspection Report 05000424/2019090 and 05000425/2019090 and Preliminary White Finding and Apparent Violation NL-18-0297, Units 1 and 2 - Notice of Violation and Proposed Imposition of Civil Penalty Method of Payment2018-03-15015 March 2018 Units 1 and 2 - Notice of Violation and Proposed Imposition of Civil Penalty Method of Payment NL-17-0844, Reply to a Notice of Violation; EA-17-0142017-05-23023 May 2017 Reply to a Notice of Violation; EA-17-014 NL-17-0384, Response to EA-17-014, Preliminary White Finding and Related Apparent Violation from Inspection Report 05000424/2017503 and 05000425/20175032017-03-16016 March 2017 Response to EA-17-014, Preliminary White Finding and Related Apparent Violation from Inspection Report 05000424/2017503 and 05000425/2017503 NL-15-0723, Reply to a Notice of Violation; EA-14-158, Inspection Report Nos. 05000424/2014009 and 05000425/20140092015-04-21021 April 2015 Reply to a Notice of Violation; EA-14-158, Inspection Report Nos. 05000424/2014009 and 05000425/2014009 NL-09-0124, Units 1 & 2, Additional Information Regarding NRC Supplemental Inspection Report 05000424-08-009 and 05000425-08-0092009-02-0202 February 2009 Units 1 & 2, Additional Information Regarding NRC Supplemental Inspection Report 05000424-08-009 and 05000425-08-009 ML0300307032002-12-20020 December 2002 Supplemental Response to Notice of Violation Dated May 29, 1996 (EA 95-171) 2023-05-01
[Table view] |
Text
B. Keith Taber Southern Nuclear Vice President Operating Company, Inc.
Vogtle- Units 1 & 2 7821 River Road Waynesboro, GA 30830 APR 2 1 20J5 Tel 706.848.3151 Fax 706.826.3321 SOUTHERN A COMPANY Docket Nos. : 50-424 NL-1 5-0723 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant, Units 1 & 2 Reply to a Notice of Violation; EA-1 4-1 58 Inspection Report NOS. 05000424/201 4-009 and 05000425/20 1 4-009
References:
1 . NRC letter to Southern Nuclear Operating Company, " Vogtle Electric Generating Plant, NRC Inspection Report Number 05000424/201 4009 and 05000425/201 4009, Preliminary Greater than Green Finding and Related Apparent Violation ", dated January 22, 20 1 5.
- 2. SNC letter to NRC, Vogtle Electric Generating Plant, Response to Preliminary White Finding from Inspection Report 05000424/201 4-009 and 05000425/201 4-009, dated January 30, 201 5.
- 3. SNC letter to NRC, Vogtle Electric Generating Plant, Response to Preliminary White Finding from Inspection Report 05000424/201 4-009 and 05000425/201 4-009, dated February 1 9, 201 5.
- 4. NRC letter to SNC, Vogtle Electric Generating Plant - Final Significance Determination of White Finding, Notice of Violation and Assessment Followup Letter (Inspection Report NOS. 05000424/20 1 4-009 and 05000425/201 4-009), dated March 30, 201 5.
Ladies and Gentlemen:
By letter dated March 30, 201 5, the Nuclear Regulatory Commission (NRC) staff notified Southern Nuclear Operating Company (SNC) of the final significance determination of the preliminary White finding discussed in NRC inspection Report 05000424, 425/201 4-009 and a Notice of Violation associated with a White significance determination process (SOP) finding. The violation involved a Type B quantity of radioactive waste being shipped in a Type A cask by SNC to the Energy Solutions radioactive waste processing facility located in Barnwell, South Carolina. SNC agrees with the NRC staff on the facts regarding the finding and, pursuant to the provisions of 1 0 CFR 2.20 1 , submits the required response to the violation as an Enclosure to this letter.
U.S. Nuclear Regulatory Commission NL-1 5-0723 Page 2 SNC does not appeal the NRC staff's significance determination for the identified White finding. SNC also understands that the N RC plans to conduct a supplemental inspection in accordance with Inspection Procedure 95001 ,
"Supplemental Inspection for One or Two White Inputs in a Strategic Performance Area". SNC will provide notification of our readiness.
This letter contains no N RC commitments. If you have any questions, please contact George Gunn at (706) 826-3596.
Respectfully submitted, B. Keith Taber Vice President Vogtle 1 & 2 BKTkb/lac
Enclosure:
Reply to a Notice of Violation; EA-1 4- 1 58 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. D. R. Madison, Vice President - Fleet Operations Mr. M. D. Meier, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Engineering Mr. G.W. Gunn, Regulatory Affairs Manager - Vogtle 1 & 2 RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, N RR Senior Project Manager - Vogtle 1 & 2 Mr. L. M. Cain, Senior Resident Inspector - Vogtle 1 & 2
Vogtle Electric Generating Plant, Units 1 & 2 Enclosure Reply to a Notice of Violation; EA-15-158 Inspection Report NOS. 05000424/2014-009 and 05000425/2014-009
Enclosure to N L-1 5-0723 Reply to Notice of Violation; EA-1 4-1 58 Restatement of Violation 050000424/201 4-009 and 05000425/201 4-009 During an NRC inspection completed on December 1 2, 20 1 4, a violation of NRC requirements was identified. In accordance with the NRC Enforcement Policy, the violation is listed below.
Vogtle Electric Generating Plant TS 5.4. 1 , Procedures, requires written procedures as recommended by Regulatory Guide 1 .33.
Regulatory Guide 1 .33, Appendix A, Section 7, recommends in part, procedures for control of radioactive material to minimize potential releases of materials to the environment, and personnel exposure from spent resin and filter sludge handling.
Procedure 461 1 1 -C, "Storage of Radwaste in Outdoor Process Shields, "
requires the licensee to maintain records of resin i n high integrity containers (HIC) being stored on the storage pad, including specific information describing the contents of each HIC and the process shield number.
1 0 CFR 71 . 1 4 states in part, a licensee is exempt from the Type B packaging requirements, provided that the package contains Low Specific Activity (LSA) , and that the external radiation dose rate is less than or equal to 1 0 mSv/h (1 rem/h) , at a distance of 3 meters from the unshielded material.
Contrary to the above, from June 1 9, 201 2, to June 24, 201 4, the licensee failed to maintain records of resin in HICs being stored on the storage pad, including specific information describing the contents and process shield number. Specifically, information regarding the location and contents of the HICs was not updated when the contents of process shield
- 1 0 were changed. As a result, on June 24, 20 1 4, the licensee used a Type A container to ship radioactive waste that exceeded a Type A quantity. Additionally, the HIC from process shield # 1 0 had an external radiation dose rate that exceeded 1 0 mSv/h ( 1 rem/h) at 3 meters from the unshielded material, and therefore did not meet the requirements to be exempted from Type B packaging.
This violation is associated with a White significance determination process (SOP) finding.
Southern Nuclear Operating Company (SNC) does not contest the violation.
E 1 -1
Enclosure to NL-1 5-0723 Reply to Notice of Violation; EA- 1 4-1 58
- 1. Reason for the Violation On June 24, 20 1 4, a Type A shipping cask containing a Type B quantity of radioactive waste was shipped by Southern Nuclear Operating Company (SNC) from the Vogtle Electric Generating Plant (VEGP), Units 1 and 2, to the Energy Solutions radioactive waste processing facility located in Barnwell, South Carolina. The serial number of the High Integrity Container (HIC) containing the spent resin was not verified when it was removed from its storage process shield and placed into the shipping cask, with the result that in this singular case, a HIC with a Type B quantity of spent resin requiring a Type B shipping cask was transported in a Type A shipping cask.
On June 1 1 , 201 4, a High Integrity Container (HIC) was prepared for shipment with what was expected to be a Type A quantity of radioactive waste from VEGP to Energy Solutions, a radioactive waste processor located in Barnwell, South Carolina.
The HIC intended for shipment was S/N #003698-1 9, which was assumed by Radiation Protection (RP) staff to be in Process Shield #1 0 based on data sheets showing HIC locations. However, in the course of a program of resampling HICs for possible waste reclassification, some HICs had been relocated to different process shields without completion of new data sheets. As a result, records of resin in HICs being stored on the storage pad were not properly maintained. In preparation for shipment, Process Shield # 1 0 was opened, the top of the HIC was surveyed, and then the HIC was removed from the process shield and placed into a Type A shipping cask, without verifying the HIC serial number.
On June 23, 201 4, the loaded DOT 7A Type A shipping cask was surveyed. External dose rates on the Type A cask met all transportation requirements of 49 CFR 1 73.441 and the shipping documentation was prepared. On June 24, 201 4, the cask was transported to the Energy Solutions Barnwell Processing Facility. On June 25, 20 1 4, Energy Solutions informed SNC that the HIC they had received was not S/N
- 003698-1 9 as indicated on the shipping manifest, but was actually S/N #6051 63-02.
On June 26, 20 1 4, SNC personnel traveled to Energy Solutions in Barnwell and confirmed that an incorrect HIC had been shipped.
Upon investigation by SNC, it was found that HIC S/N #6051 63-02 contained a Type B quantity of radioactive waste (spent resin) which required shipment in a Type B cask. Upon survey of the HIC at the Barnwell facility, it was determined by Energy Solutions and SNC personnel to have an unshielded 3 meter dose rate of 1 .3 Rem/hour, measured from the bottom of the HIC. This dose rate exceeded the limits described in 49 CFR 1 73.427(a) ( 1 ) for a radioactive material package to be shipped as Radioactive Material LSAISCO. The unshielded dose rate also exceed the criterion for exemption in 1 0 CFR 71 . 1 4(b)(3)(i). Therefore, a shipping cask certified by the NRC (Type B shipping cask) should have been utilized for transportation of the HIC.
E1 -2
Enclosure to NL-1 5-0723 Reply to Notice of Violation; EA- 1 4- 1 58
- 2. Corrective Steps Taken and Results Achieved Radioactive waste shipping activities across the SNC fleet were suspended pending review of this event and implementation of fleet-wide corrective actions. A detailed review of radioactive waste shipping procedures was performed with radioactive waste shipping personnel across the fleet to ensure alignment and weaknesses were addressed at all sites. SNC has completed an Apparent Cause Determination and is performing a Root Cause Determination. The following immediate corrective actions have been completed:
- Oral boards were conducted with radioactive waste shipping personnel to assess and coach standards and behaviors. Emphasis was placed on human performance tool usage. Training emphasized that signature on the shipping manifest certifies that the material has been properly classified, packaged and labeled and is in proper condition for transportation according to applicable regulation.
- Oral boards were also performed with RP supervisory personnel to ensure oversight roles are clearly understood, and supervisory oversight is required on all high risk radiological activities.
- A peer review for the next waste shipment was conducted by Plant Farley and Corporate qualified RP Waste Shippers. The peer review entailed having additional oversight at Plant Vogtle to ensure the shipment was packaged and surveyed appropriately and independently verified to be correct.
- Radioactive waste/material shipment procedures were revised to require visual verification of the HIC serial number, with a verification step added to the cask and HIC inspection checklist. Procedure revisions also enhanced the inventory control of liners.
- A fleet Focused Area Self-Assessment (FASA) of RP Radwaste was performed and determined the corrective action measures to be effective.
The FASA team was composed of Southern Nuclear Corporate and Plant Vogtle station RP personnel and also included industry peers.
- The ALARA Briefing record for the HIC loading Radiation Work Permit was revised to require verification of the liner serial number, verification of the correct process shield location, and designation of individuals by name to perform the verification tasks. Approval by the Fleet RP Manager and Site Plant Manager was required prior to resumption of radioactive waste shipping. Radioactive waste shipping for VEGP was resumed on September 5, 201 4.
- An Apparent Cause Determination has been completed.
E1 -3
Enclosure to NL-15-0723 Reply to Notice of Violation; EA-14-158
- 3. Corrective Steps to be Taken to Avoid Further Violations The causal determination has been escalated and a Root Cause determination is currently in progress. Additional corrective actions may emerge from the Root Cause investigation.
- 4. Date When Full Compliance Will Be Achieved SNC is in full compliance. The subject HIC was placed into a Type B cask and shipped to the Energy Solutions facility in Erwin, Tennessee for processing and subsequent disposal. Based on corrective actions and reviews completed, SNC has determined that radwaste shipments are being adequately performed and accurately documented.
E1-4