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| | number = ML14202A577 | | | number = ML14202A577 |
| | issue date = 07/17/2014 | | | issue date = 07/17/2014 |
| | title = 10 CFR 71.95 Report on the TN-RAM Package | | | title = CFR 71.95 Report on the TN-RAM Package |
| | author name = McCartney E | | | author name = McCartney E |
| | author affiliation = NextEra Energy Point Beach, LLC | | | author affiliation = NextEra Energy Point Beach, LLC |
Revision as of 19:25, 3 April 2019
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Category:Letter
MONTHYEARIR 05000266/20240032024-11-0505 November 2024 Integrated Inspection Report 05000266/2024003 and 05000301/2024003 ML24295A1142024-10-31031 October 2024 Suppl Env Audit Summary Letter W/Enclosure 1 L-2024-176, Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums2024-10-30030 October 2024 Annual 10 CFR 140.21 Licensee Guarantees of Payment of Deferred Premiums ML24295A0862024-10-21021 October 2024 Notification of NRC Baseline Inspection and Request for Information Inspection Report 0500026/2025002 L-2024-160, Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41)2024-10-21021 October 2024 Core Operating Limits Report (COLR) Unit 2 Reload Cycle 41 (U2C41) L-2024-169, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes2024-10-15015 October 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site- Specific Annexes L-2024-120, LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization2024-10-0808 October 2024 LAR 301 - Revise Renewed Facility Operating Licenses to Adopt an Alternative Approach for Addressing Seismic Risk in 10 CFR 50.69 Risk-Informed Categorization L-2024-118, Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1)2024-10-0808 October 2024 Fleet License Amendment Request to Relocate Staff Qualifications from Technical Specifications to the Quality Assurance Topical Report (FPL-1) L-2024-158, Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-25025 September 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20240112024-09-18018 September 2024 Biennial Problem Identification and Resolution Inspection Report 05000266/2024011 and 05000301/2024011 L-2024-136, Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-09-16016 September 2024 Supplement to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes L-2024-145, Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency2024-09-0909 September 2024 Notification of Deviation from EPRI MRP-227, Revision 1-A Baffle Bolt Inspection Frequency ML24207A0202024-08-28028 August 2024 Response to Request for Re-Engagement Regarding the Subsequent License Renewal Environmental Review for Point Beach Nuclear Plant, Units 1 and 2 (Docket Numbers: 50-0266 and 50-0301) IR 05000266/20240052024-08-21021 August 2024 Updated Inspection Plan for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2024005 and 05000301/2024005) IR 05000266/20240022024-08-13013 August 2024 Integrated Inspection Report 05000266/2024002 and 05000301/2024002 L-2024-131, Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-08-0909 August 2024 Response to Request for Additional Information Regarding License Amendment Request 300, Modify Containment Average Air Temperature Requirements ML24163A0012024-08-0505 August 2024 LTR-24-0119-1-1 Response to Nh Letter Regarding Review of NextEras Emergency Preparedness Amendment Review ML24214A3092024-08-0202 August 2024 Confirmation of Initial License Examination L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections2024-07-24024 July 2024 License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections L-2024-125, Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes2024-07-24024 July 2024 Notice of Intent to Provide Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes ML24194A1802024-07-24024 July 2024 – Revision to the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule IR 05000266/20244012024-07-23023 July 2024 Public - Point Beach Nuclear Plant Cyber Security Inspection Report 05000266/2024401 and 05000301/2024401 ML24193A2432024-07-12012 July 2024 – Interim Audit Summary Report in Support of Review of License Amendment Requests Regarding Fleet Emergency Plan L-2024-116, Preparation and Scheduling of Operator Licensing Examinations2024-07-11011 July 2024 Preparation and Scheduling of Operator Licensing Examinations L-2024-114, Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal2024-07-10010 July 2024 Quality Assurance Topical Report (FPL-1 Revision 31 Annual Submittal IR 05000266/20240102024-07-10010 July 2024 Age-Related Degradation Inspection Report 05000266/2024010 and 05000301/2024010 L-2024-105, License Amendment Request 300, Modify Containment Average Air Temperature Requirements2024-06-26026 June 2024 License Amendment Request 300, Modify Containment Average Air Temperature Requirements L-2024-107, Schedule for Subsequent License Renewal Environmental Review2024-06-25025 June 2024 Schedule for Subsequent License Renewal Environmental Review ML24176A2242024-06-24024 June 2024 Notification of an NRC Biennial Licensed Operator Requalification Program Inspection and Request for Information L-2024-102, Official Service List Update2024-06-19019 June 2024 Official Service List Update ML24149A2862024-06-12012 June 2024 NextEra Fleet - Proposed Alternative Frr 23-01 to Use ASME Code Case N-752-1, Risk-Informed Categorization and Treatment for Repair/Replacement Activities in Class 2 and 3 Systems Section X1, Division 1 (EPID L-2023-LLR-0009) - Letter L-2024-093, Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision2024-06-10010 June 2024 Steam Generator Divider Plate Assemblies Bounding Analysis Evaluation for Aging Management Commitment 14 Revision IR 05000266/20244202024-06-0505 June 2024 Security Baseline Inspection Report 05000266/2024420 and 05000301/2024420 ML24149A1922024-05-28028 May 2024 Notification of NRC Baseline Inspection and Request for Information ML24141A1382024-05-20020 May 2024 Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection.Docx ML24127A0632024-05-0606 May 2024 Supplemental Information to License Amendment Request to Adopt Common Emergency Plan with Site-Specific Annexes IR 05000266/20243012024-04-29029 April 2024 NRC Initial License Examination Report 05000266/2024301; 05000301/2024301 L-2024-067, Annual Monitoring Report2024-04-26026 April 2024 Annual Monitoring Report ML24116A0402024-04-23023 April 2024 Periodic Update of the Updated Final Safety Analysis Report ML24071A0912024-04-22022 April 2024 Issuance of Relief Request I6-RR-03 - Extension of the Unit 2 Steam Generator Primary Nozzle Dissimilar Metal Welds Sixth 10-Year Inservice Inspection Program Interval IR 05000266/20240012024-04-11011 April 2024 Integrated Inspection Report 05000266/2024001 and 05000301/2024001 L-2024-030, Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements2024-03-27027 March 2024 Supplement to Relief Request CISl-03-01 for Relief Concerning Containment Unbonded Post-Tensioning System Inservice Inspection Requirements L-2024-043, Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules2024-03-25025 March 2024 Revised Reactor Vessel Materials Surveillance Capsule Withdrawal Schedules L-2024-011, And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications2024-03-13013 March 2024 And Point Beach, Units 1 and 2 - 10 CFR 50.46 Annual Reporting of Changes to, or Errors in Emergency Core Cooling System Models or Applications IR 05000266/20230062024-02-28028 February 2024 Annual Assessment Letter for Point Beach Nuclear Plant, Units 1 and 2 (Report 05000266/2023006 and 05000301/2023006) ML24053A3732024-02-22022 February 2024 Operator Licensing Examination Approval Point Beach, March 2024 L-2024-020, Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections2024-02-22022 February 2024 Refueling Outage Owners Activity Report (OAR-1) Unit 1 for Inservice Inspections ML24036A2652024-02-0505 February 2024 Notice of Inspection and Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000266/2024010 and 05000301/2024010 IR 05000266/20230042024-02-0101 February 2024 Integrated Inspection Report 05000266/2023004 and 05000301/2023004 ML24030A0352024-01-30030 January 2024 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 2024-09-09
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July 17, 2014 Mr. Mark Lombard, Director Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington DC 20555-0001 ATTN: Document Control Desk Point Beach Nuclear Plant, Units 1 and 2 Dockets 50-266, 50-301 and 72-005 Renewed License Nos. DPR-24 and DPR-27 10 CFR 71.95 Report on the TN-RAM Package NEXT era E N ERG Y e POINT BEACH NRC 2014-0047 10 CFR 71.95
Reference:
(1) AREVA TN letter to NRC, dated June 18, 2014, Report Pursuant to 10 CFR 71.95(a)(3) and (b) of As-Built Discrepancies in the TN-RAM Packaging Relative to Certificate of Compliance No. 9233 (ML 14171 A358) Via Reference 1 Areva TN Americas submitted a report to the NRC providing information required by 10 CFR 71.95(a)(3) and (b) with respect to Certificate of Compliance (CoC) No. 9233, Revision 11, for the Model No. TN-RAM Package , Docket No. 71-9233. The Areva TN Americas report noted as-built discrepancies relative to CoC No. 9233 for the TN-RAM Package. The circumstances described in the report were applicable to all licensed users of the cask. The submittal contained the details surrounding the situation, an engineering evaluation which dispositions the as-built discrepancies and an affidavit related to the proprietary nature of the engineering evaluation.
NextEra was notified by Areva TN Americas of as-built discrepancies on June 19, 2014 [Enclosure].
In accordance with 10 CFR 71.95(a), NextEra is reporting use of the TN-RAM Package. NextEra Energy Point Beach, LLC, 6610 Nuclear Road, Two Rivers, WI 54241 Office of Nuclear Material Safety and Safeguards Page 2 NextEra Energy used the TN-RAM cask on August 25, 1997 to ship spent fuel pool cleanout waste, with no incident.
As concluded in the Areva report , there is no safety significance associated with the discrepancies between the safety analysis report drawings , as listed in CoC No. 9233 Section 5(a)(3), and the as-built packaging.
Currently Areva TN Americas is prohibiting the TN-RAM from use. Therefore, until the discrepancies are corrected the cask is not available for site use. If you have any questions related to this submittal , please contact Gene LeClair at 920/755-6953. Very truly yours, Next E ra Energy Point Beach, LLC Eric McCartney Site Vice President Enclosure cc: Administrator, Region Ill, USNRC Resident Inspector , Point Beach Nuclear Plant, USNRC ENCLOSURE NEXTERA ENERGY POINT BEACH, LLC POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 AREVA TN NOTIFICATION TO REGISTERED USERS 10 CFR 71.95 REPORT ON THE TN-RAM PACKAGE [Reference 1 Removed] 1 page follows Registered Users for CoC Number 9233 , Revision 11: A AREVA June 19 2014 E-38923
Subject:
Notification to Registered Users (Licensees)
Regarding a Potential Need to Report Pursuant to 10 CFR 71.95(a) of As-Built Discrepancies Relative to Certificate of Compliance No. 9233
Reference:
Letter E-38692, dated June 18, 2014, from Paul Triska (AREVA TN) to U.S. Nuclear Regulatory Commission, Report Pursuant to 10 CFR 71.95 (a)(3) and (b) of As-Built Discrepancies in the TN-RAM Packaging Relative to Certificate of Compliance No. 9233 As the certificate holder of CoC 9233 for the TN-RAM Package, AREVA TN Americas wishes to inform you with this letter of the discovery of a situation i nvolving discrepancies in the TN-RAM packaging relative to the CoC conditions. It is our understanding that this situation is reportable under 10 CFR 71.95 if you used the TN-RAM from the time of its initial fabrication until now. AREVA TN Americas is also a registered user of the TN-RAM and we have made a report via the submittal referenced above , which contains the details surrounding this situation, an engineering evaluation which dispositions the as-built discrepancies, and an affidavit related to the proprietary nature of that engineering evaluation.
The submittal also discusses preventative and corrective actions AREVA TN Americas performed, which include a June 11, 2014 application to NRC to revise CoC 9233 to correct the identified discrepancies. In order to facilitate your reporting , Enclosure 1 provides the referenced submittal in its entirely. Should you require additional information regarding this situation, please do not hesitate to contact me at (41 0)-91 0-6878. Sincerely, Don Shaw Director , Regulatory Affairs cc: Prakash Narayanan (AREVA TN Americas)
Glenn Mathues (AREVA TN Americas)
Enclosures
- 1. Letter E-38692 , dated June 18, 2014, including all enclosures.
AR E VA TN A RE VA In c. 71 3 5 M i ns tr el Way-S uit e 300-Co lumb ia , MD 2 1 045 U SA T e l.: (41 0) 9 1 0-6900 -F ax: (41 0) 9 1 0-6902 us.a r eva.co m/AR E VAT N