|
|
Line 1: |
Line 1: |
| #REDIRECT [[JAFP-08-0103, James A. FitzPatrick, Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility]] | | {{Adams |
| | | number = ML082840578 |
| | | issue date = 10/02/2008 |
| | | title = James A. FitzPatrick, Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility |
| | | author name = Dorman G |
| | | author affiliation = Entergy Nuclear Northeast, Entergy Nuclear Operations, Inc |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NMSS |
| | | docket = 05000333, 07105805 |
| | | license number = DPR-059 |
| | | contact person = |
| | | case reference number = JAFP-08-0103 |
| | | document type = Letter, Report, Miscellaneous |
| | | page count = 7 |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:.j. -Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. Fitzpatrick NPP EntergyP.O. |
| | Box 110 Lycoming, NY 13093 Tel 315-342-3840 JAFP-08-0103 October 2, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 |
| | |
| | ==Subject:== |
| | Entergy Nuclear Operations, Inc.James A. FitzPatrick Nuclear Power Plant License No. DPR-59 Docket No. 50-333 Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, SC Disposal Facility |
| | |
| | ==Reference:== |
| | |
| | South Carolina, Department of Health and Environmental Services letter to Mr. John Solowski, Radiation Protection Manager, Entergy Nuclear'Northeast/JAFNPP regarding South Carolina Radioactive Waste Transportation Permit 0031-31-08, dated April 10, 2008 |
| | |
| | ==Dear Sir or Madam:== |
| | In accordance with 10 CFR 71.95(c), Entergy Nuclear Northeast Operations, Inc., James A. FitzPatrick Nuclear Power Plant (JAF) is providing this report of a discrepancy discovered during receipt of a low level radioactive waste shipment at the disposal facility located in Barnwell, South Carolina. |
| | Following the off-loading of Duratek Transport Cask CNS cask 3-55-1 that originated from JAF, Barnwell personnel determined that the cask base plate lead-in bolt located at the 2 o'clock position was not torqued to 75 ft-lbs., as required by the cask handling procedure referenced in the Certificate of Compliance. |
| | In accordance with 10 CFR 71.95(c), a written report is required within 60 days upon discovery of an event identified in 10 CFR 71.95, paragraphs (a) or (b). JAF's original review of the event determined that the discrepancy was not reportable. |
| | Subsequent review with the NRC concluded that the discrepancy meets reporting criterion 10 CFR 71.95(a)(3) and a late report should be submitted. |
| | Attachment 1 contains the event report.There are no new commitments made in this letter.Should you have any questions or require additional information, please contact Mr.John Solowski, Radiation Protection Manager at (315) 349-6783.L\"5C JAFP-08-0103 Page 2 of 2 Sincerely, Gene Dorman Acting Licensing Manager ED:jm |
| | |
| | ==Attachment:== |
| | |
| | Event Report cc: Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch U.S. Nuclear Regulatory Commission Mail Stop 08 C2A Washington, DC 20555 Mr. E. William Brach, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission Mail Stop E3 D2M Washington, DC 20555-0001 Office of NRC Resident Inspector James A. FitzPatrick NPP P.O. Box 136 Lycoming, New York 13093 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul Eddy New York State Department of Public Services 3 Empire State Plaza Albany, New York 12223-1350 Mr. Paul Tonko, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, New York 12203-6399 Mr. Patrick L. Paquin, General Mgr.Energy Solutions 140 Stoneridge Drive Columbia, South Carolina 29210 ATTACHMENT 1 to JAFP-08-0103 James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Event Report ATTACHMENT'1 to JAFP-08-0103 |
| | : 1. ABSTRACT: On February 15, 2008, the Barnwell Disposal Facility notified JAF of the discovery of a loose base plate lead-in bolt located at the 2 o'clock position on low-level radioactive waste cask CNS 3-55-1 that was shipped from JAF. The shipment (No. 0208-13587) was classified as Radioactive Material, Type B (U) Package and was transported from JAF on February 12, 2008 as "Exclusive Use". The shipment was transported in accordance with Radioactive Material Quantities of Concern (RAMQC) program requirements. |
| | The shipment contents were irradiated hardware from the JAFspent fuel pool cleanup campaign. |
| | Verbal notification from Barnwell indicated that the loose bolt did not result in a violation of seal integrity, and radiation and contamination surveys had indicated no leakage.On April 10, 2008, JAF received written notification of an infraction from the State of South Carolina (SC), Department of Health and Environmental Control (DHEC), Bureau of Land and Waste Management. |
| | The letter identified the loose bolt discrepancy discovered by Barnwell and noted that the condition was contrary to the requirements of"Handling Procedure For The Duratek Transport Cask CNS 3-55, Certificate of Compliance 5805" and SC Radioactive Material License 097. The letter directed JAF to investigate and institute corrective measures which ensure that all handling procedures involving radioactive material transportation at JAF would be properly implemented and to provide the DHEC documentation of the corrective measures not later than May 12, 2008.2. NARRATIVE: |
| | On February 11, 2008, CNS cask 3-55-1 was prepared by Energy Solutions, Inc. (ES)personnel at the JAF site for shipment of irradiated hardware to the Barnwell Waste Management Facility. |
| | Model CNS 3-55 casks are comprised of a steel-encased, lead-shielded cylindrical body sealed to a base plate by two silicone o-rings and secured by twelve base plate bolts. The base plate bolts were torqued to 75 ft-lbs, as required by the ES cask handling procedure. |
| | Both ES and JAF personnel completed the verification and sign off checklist for the base plate bolt torque values as required by the ES cask handling procedure. |
| | Impact limiters (top and bottom) were also installed and secured to the cask body, each using six impact limiter bolts which were wrench tightened. |
| | ES procedures did not specify a torque value requirement nor independent verification for the installation of the impact limiter bolts.On February 12, 2008, CNS cask 3-55-1 was shipped from JAF to the Barnwell facility.On February 14, 2008, the cask was receipt inspected, surveyed, off loaded from the transport trailer and reloaded to a yard trailer in preparation for the cask to be taken to the slit trench for disposal. |
| | On February 15, 2008, following removal of the impact limiter, a Barnwell technician noted that a base plate lead-in bolt at the 2 o'clock position was loose (less than hand tight). On that same day, JAF was notified of the discovery by the ES Licensing Manager at the Barnwell facility. |
| | During the notification, the ES Licensing Manager reported that there was no violation of cask seal integrity, and-radiation and contamination surveys indicated no leakage.1 of 4 ATTACHMENT 1 to JAFP-08-0103 |
| | : 2. NARRATIVE (con't): Status of Components: |
| | Based upon surveys of the shipping cask during the receiving process, the structural integrity of the cask was not affected by the discrepancy. |
| | There was no indication of leakage or shifting of contents. |
| | The discrepancy involved a single closure bolt on the shipping cask. As described in Section 2 of the CNS 3-55 cask safety analysis report, a single loose bolt is within the analyzed design basis of the cask.ii. Dates and approximate times of occurrences: |
| | The discrepancy was discovered on February 15, 2008 at the Barnwell, SC facility. |
| | JAF personnel were notified on that same day by the ES Licensing Manager at the Barnwell facility.iii. Cause of component or system failure: JAF has notified ES, the owner of the cask, of the identified deficiency. |
| | Since JAF does not own the cask or its design basis, we can not definitively determine the cause of the event. Our apparent cause evaluation identified inadequate procedural guidance for installing the impact limiter as a potential cause for the event. Model CNS 3-55 casks are comprised of a cask base plate which is secured to the cask body by twelve base plate bolts and sealed with two silicone o-rings. As part of the installation process, an impact limiter is attached to the cask body after securing the base plate to the cask. The twelve base plate bolts are secured, by procedure, to 75 ft-lbs of torque. The six impact limiter bolts are then wrench tightened to an unspecified torque value. Since the lower impact limiter is secured to the same flange as the cask base plate, compression of the base plate bolting may have occurred upon wrench -tightening of the impact limiter bolts, thereby, causing relief of the base plate bolt during transport. |
| | iv. Failure mechanism: |
| | As noted above, JAF can not definitively determine the failure mechanism. |
| | A potential failure mechanism is wrench tightening of the impact limiter bolts into the same flange as the base plate bolts without specific torque value criteria. |
| | The wrench tightening of the impact limiter bolts might have resulted in compression on the base plate bolting, thereby causing relief of the torque value on a base plate bolt during transport to the Barnwell facility.v. Secondary functions affected: The discrepancy involved a single closure bolt on the shipping cask, and did not affect any secondary functions or components. |
| | vi. Method of discovery: |
| | The discrepancy was discovered during off loading of the liner into the slit trench at the Barnwell, SC facility.2 of 4 t I ATTACHMENT 1 to JAFP-08-0103 |
| | : 2. NARRATIVE (con't): vii. Human performance root cause: The event was not primarily the result of human performance deficiencies. |
| | The discrepancy may have been caused by the design of the cask and inadequate ES procedures relating to the installation of the cask impact limiter. ES personnel's failure to incorporate lessons learned from a similar event and JAF's limited initial screening of operating experience within the plant operating experience program were contributing causes.viii. Manufacture/Model number: Shipping Cask No. 3-55-1 and ES Certificate of Compliance No. 5805.ix. Quantities/Content: |
| | Radioactive waste shipment No. 0208-13587 was classified as a Radioactive Material, Type B (U) Package. The shipment contents were irradiated hardware from the JAF spent fuel pool cleanup campaign.3. SAFETY CONSEQUENCES: |
| | There were no direct or likely challenges to nuclear or industrial safety as a result of this event. The discrepancy involved a single closure bolt. Section 2 of the cask'safety analysis report shows that failure of 1 to 3 closure bolts will not result in loss of the cask base plate. Radiological surveys of the shipping cask were conducted at the Barnwell, SC facility upon discovery of the deviation, and no contamination or leakage was detected.4. CORRECTIVE ACTIONS: After performing an apparent cause evaluation, JAF performed the following corrective actions: 0 Notified ES that the CNS 3-55 casks will not be used at JAF until ES determines the cause of the event and implements effective corrective actions to prevent recurrence. |
| | 0 Revised JAF's cask handling procedure checklist (RP-OPS-05-07) to include a QA hold point for verification that a second torque check is performed with the cask in the horizontal position.0 Counseled JAF Radiation Protection staff to lower the threshold for entering deviations relating to radioactive waste transport activities into the corrective action program (CAP).3 of 4 |
| | .!A 1 4 ATTACHMENT 1 to JAFP-08-0103 |
| | : 5. SIMILAR EVENTS: A similar industry event occurred in February, 2007 when Constellation Energy's Nine Mile Point Nuclear Generating Station made a shipment using the same cask.6. CONTACT INFORMATION: |
| | For additional information regarding this event, please contact Mr. John Solowski, Radiation Protection Manager, at 315-349-6783. |
| | : 7. EXPOSURE INFORMATION: |
| | Radiological surveys of the shipping cask were conducted at the Barnwell, SC facility upon discovery of the deviation. |
| | No contamination or leakage were detected, therefore no unexpected radiological exposure to individuals occurred.4 of 4}} |
|
---|
Category:Letter
MONTHYEARIR 05000333/20240052024-08-29029 August 2024 Updated Inspection Plan for James A. Fitzpatrick Nuclear Power Plant (Report 05000333/2024005) ML24222A6772024-08-0909 August 2024 Response to Request for Additional Information for Application to Revise Technical Specifications to Adopt TSTF-591-A, “Revise Risk Informed Completion Time (RICT) Program” Revision 0 and Revise 10 CFR 50.69 License Condition IR 05000333/20240022024-08-0707 August 2024 Integrated Inspection Report 05000333/2024002 JAFP-24-0034, 10 CFR 50.46 Annual Report2024-07-31031 July 2024 10 CFR 50.46 Annual Report ML24208A0492024-07-30030 July 2024 Notice of Consideration of Issuance of Amendments to Facility Operating Licenses and Proposed No Significant Hazards Consideration Determination (Letter) JAFP-24-0036, Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-07-29029 July 2024 Supplement to License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0033, Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test2024-07-23023 July 2024 Response to Request for Information Pertaining to a Licensed Operator Positive Fitness-For-Duty Test IR 05000333/20244032024-07-18018 July 2024 Biennial Problem Identification and Resolution Inspection Report 05000333/2024403 (Cover Letter Only) IR 05000333/20244012024-07-15015 July 2024 Security Baseline Inspection 05000333/2024401 RS-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions ML24190A1932024-07-0909 July 2024 Correction Letter of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance IR 05000333/20240102024-07-0808 July 2024 Commercial Grade Dedication Inspection Report 05000333/2024010 ML24184A1662024-07-0303 July 2024 Senior Reactor and Reactor Operator Initial License Examinations ML24136A1162024-06-26026 June 2024 Issuance of Amendment No. 355 Revise Technical Specifications Section 3.4.3.1, Safety Relief Valves Setpoint Lower Tolerance ML24176A2412024-06-24024 June 2024 Licensed Operator Positive Fitness-for-Duty Test RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations JAFP-24-0026, Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance2024-06-12012 June 2024 Supplement to License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (Srvs) Setpoint Lower Tolerance ML24079A0762024-05-23023 May 2024 Issuance of Amendments to Adopt TSTF 264 JAFP-24-0023, 2023 Annual Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Annual Radiological Environmental Operating Report IR 05000333/20240012024-05-0909 May 2024 Integrated Inspection Report 05000333/2024001 RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report2024-04-25025 April 2024 2023 Annual Radioactive Effluent Release Report JAFP-24-0019, 2023 REIRS Transmittal of NRC Form 52024-04-18018 April 2024 2023 REIRS Transmittal of NRC Form 5 ML24106A0152024-04-15015 April 2024 Request for Withholding Information from Public Disclosure Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling ML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition ML24107A6972024-04-12012 April 2024 Engine Systems, Inc Part 21 Report Re EMD Cylinder Liner Water Leak RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report ML24068A0532024-03-28028 March 2024 Issuance of Amendment No. 354 Revise Technical Specifications Section 3.3.1.2, Source Range Monitors Instrumentation JAFP-24-0014, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-03-25025 March 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-24-0010, Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2024-02-29029 February 2024 Response to Request for Additional Information for License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance IR 05000333/20230062024-02-28028 February 2024 Annual Assessment Letter for James A. FitzPatrick Nuclear Power Plant (Report 05000333/2023006) JAFP-24-0009, Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2024-02-28028 February 2024 Response to Request for Additional Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis IR 05000333/20230042024-02-0707 February 2024 Integrated Inspection Report 05000333/2023004 and Independent Spent Fuel Storage Installation Inspection Report 07200012/2023001 ML24037A0102024-02-0606 February 2024 Requalification Program Inspection ML24018A0012024-01-18018 January 2024 Notification of Commercial Grade Dedication Inspection (05000333/2024010) and Request for Information ML24004A2302024-01-0808 January 2024 Project Manager Reassignment ML23356A0832024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0058 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23278A1292023-12-14014 December 2023 Units 1 & 2; Limerick, Units 1 & 2; Nine Mile Point, Units 1 & 2; and Peach Bottom, Units 2 & 3 -Revision to Approved Alternatives to Use Boiling Water Reactor Vessel and Internals Project Guidelines JAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications IR 05000333/20234012023-12-0808 December 2023 Cybersecurity Inspection Report 05000333/2023401 (Cover Letter Only) RS-23-126, Request for Exemption from 10 CFR 2.109(b)2023-12-0707 December 2023 Request for Exemption from 10 CFR 2.109(b) JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use IR 05000333/20230032023-11-13013 November 2023 Integrated Inspection Report 05000333/2023003 ML23317A1192023-11-10010 November 2023 Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums IR 05000333/20230102023-10-26026 October 2023 Biennial Problem Identification and Resolution Inspection Report 05000333/2023010 JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use IR 05000333/20233012023-10-19019 October 2023 Initial Operator Licensing Examination Report 05000333/2023301 2024-08-09
[Table view] Category:Report
MONTHYEARRS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML19301A5052019-08-13013 August 2019 JAF-CALC-NBI-00205 Setpoint Calculation for Vessel Lo-Lo Lvl Primary Containment Isolation Function (02-3LT-57A,B and 02-3STU-258A,B) ML18019A2692018-02-12012 February 2018 Flood Hazard Mitigation Strategies Assessment JAFP-17-0085, High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic2017-08-30030 August 2017 High Frequency Confirmation Report for March 12, 2012, Information Request Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1, Seismic JAFP-17-0084, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2017-08-29029 August 2017 Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) JAFP-17-0078, Focused Evaluation Summary Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2017-07-27027 July 2017 Focused Evaluation Summary Pursuant to 10 CFR 50.54(f) Request for Information Regarding Recommendation 2.1: Flooding of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-17-0054, James a FitzPatrick - Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay2017-05-25025 May 2017 James a FitzPatrick - Submittal of Stress Analysis Summary for the 24-10-130 Weld Overlay ML17110A2742017-04-20020 April 2017 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI Division 1 ML16043A4112016-02-18018 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask JAFP-15-0036, J.A. Fitzpatrick Flood Hazard Reevaluation Report - Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuskushima Dai-2015-03-12012 March 2015 J.A. Fitzpatrick Flood Hazard Reevaluation Report - Response to NRC Request for Information Per 10 CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fuskushima Dai-ichi ML15007A0902015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) ML15007A1502015-01-0707 January 2015 Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. JAFP-15-0007, Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accid2015-01-0707 January 2015 Seismic Walkdown Report Update - Entergy'S Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Re the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident. JAFP-14-0143, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. JAFP-14-0094, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2014-08-0101 August 2014 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14073A1552014-04-0101 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML14007A6812014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14043A4282014-02-15015 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for James A. FitzPatrick Nuclear Power Plant, TAC Nos.: MF1077 ML13273A6912013-08-20020 August 2013 Redacted - Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask ML13247A0362013-08-20020 August 2013 Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask JAFP-13-0096, James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2013-08-0101 August 2013 James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models JAFP-13-0035, Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 232013-04-17017 April 2013 Response to Request for Additional Information on Core for Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment #23 ML12342A1402012-11-27027 November 2012 Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-12-0135, Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident JAFP-12-0134, FitzPatrick - Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 FitzPatrick - Seismic Walkdown Report, Response to NRC Request for Information Per 10 CFR 50.54 (F) Re the Seismic Aspect of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML12342A1422012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 551 Through 573 JAFP-12-0134, Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 283 Through 5732012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 2 of 3, Attachment C, Pages 283 Through 573 ML12342A1392012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 573 ML12342A1382012-11-21021 November 2012 Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3 JAFP-12-0134, Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 5732012-11-21021 November 2012 Engineering Report JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3, Attachment C, Pages 74 Through 573 JAFP-12-0134, Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 32012-11-21021 November 2012 Engineering Report, JAF-RPT-12-00015, Rev. 0, Jaf Seismic Walkdown Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3 Seismic, Book 1 of 3 JAFP-12-0122, Core Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment 232012-09-28028 September 2012 Core Plate Rim Hold Down Bolting, Plant Specific Analysis and Inspection Plan, License Renewal Commitment #23 ML13163A2662012-05-18018 May 2012 from Bhalchandra Vaidya to Samson Lee: G20120172, 2.206 Petition ML13162A6272012-02-20020 February 2012 Summary of R1 Containment Vents ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1125101872011-09-0808 September 2011 NRC Investigation Report Nos. 1-2009-041, 1-2010-019, and 1-2010-031 ML1024601002010-09-0202 September 2010 Enclosure 2, RA-ENO-EP1-10-135, Response to NRC Supplemental RAIs 1, 4, 5, and 6 for James a FitzPatrick Cycle 20 SLMCPR Submittal ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants JAFP-09-0091, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models2009-07-31031 July 2009 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-09-0056, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.482009-05-11011 May 2009 Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.48 JAFP-08-0131, Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C2008-12-0404 December 2008 Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C ML0835903392008-12-0404 December 2008 Enclosure 2, Structural Integrity Associates, Inc. Calculation 0800769.311 Crack Growth Analysis for Recirculation Inlet Nozzle N-2C JAFP-08-0131, Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report2008-12-0303 December 2008 Enclosure 3, Structural Integrity Associates, Inc. Calculation 0800769.316 Reconciliation of Recirculation Inlet N2 Nozzle-to-Safe End Weld Overlay Repair with Nozzle Stress Report ML0831006632008-11-19019 November 2008 Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-CRV-01 JAFP-08-0103, Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility2008-10-0202 October 2008 Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility ML0810102772008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 2021-01-04
[Table view] Category:Miscellaneous
MONTHYEARML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18019A2692018-02-12012 February 2018 Flood Hazard Mitigation Strategies Assessment JAFP-17-0084, Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2017-08-29029 August 2017 Report of Full Compliance with March 12, 2012, Commission Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML17110A2742017-04-20020 April 2017 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI Division 1 ML16043A4112016-02-18018 February 2016 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review JAFP-15-0129, Submittal of 10 CFR 71.95 Report Involving 8-120B Cask2015-11-0606 November 2015 Submittal of 10 CFR 71.95 Report Involving 8-120B Cask ML15007A0902015-02-12012 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) JAFP-14-0143, Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The.2014-12-30030 December 2014 Expedited Seismic Evaluation Process Report (CEUS Sites), Response NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from The. JAFP-14-0094, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2014-08-0101 August 2014 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models ML14073A1552014-04-0101 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13247A0362013-08-20020 August 2013 Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask ML13273A6912013-08-20020 August 2013 Redacted - Letter from R. Dale Roberts 10 CFR 71.95 Report on the 8-120B Cask JAFP-13-0096, James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models2013-08-0101 August 2013 James a FitzPatrick Nuclear Power Plant, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System Evaluation Models JAFP-12-0135, Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2012-11-27027 November 2012 Flooding Walkdown Report - Entergys Response to NRC Request for Information Pursuant to 10CFR50.54(f) Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML13162A6272012-02-20020 February 2012 Summary of R1 Containment Vents ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants ML1125101872011-09-0808 September 2011 NRC Investigation Report Nos. 1-2009-041, 1-2010-019, and 1-2010-031 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants JAFP-09-0091, 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models2009-07-31031 July 2009 10 CFR 50.46 Annual Report - Changes and Errors in Emergency Core Cooling System (ECCS) Evaluation Models JAFP-09-0056, Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.482009-05-11011 May 2009 Summary of Plant and Independent Spent Fuel Storage Installation Changes, Tests, and Experiments for 2007 and 2008 as Required by 10 CFR 50.59 and 10 CFR 72.48 ML0831006632008-11-19019 November 2008 Request for Additional Information Third 10-Year Interval Inservice Inspection Program Plan Relief Request RR-CRV-01 JAFP-08-0103, Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility2008-10-0202 October 2008 Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, Sc Disposal Facility ML0810102772008-09-0808 September 2008 Renewed Facility Operating License No. DPR-59 / Appendix C - Additional Conditions ML0805905802008-02-15015 February 2008 List of Requesters Fitzpatrick ML0805905792008-02-14014 February 2008 Foia/Pa Cases Received from 02/12/07 to 02/12/08 ML0711601862007-05-21021 May 2007 Biological Assessment for Species Under the Jurisdiction of the U.S. Fish and Wildlife Service - James A. FitzPatrick Nuclear Power Plant License Renewal Review ML0710004922007-03-26026 March 2007 Usfws Threatened and Endangered Species System (Tess) - New York ENOC-07-00002, Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 20062007-02-28028 February 2007 Units 1, 2 & 3; Pilgrim and Vermont - Fitness-for-Duty Program Performance Report for the Period July 2006 - December 2006 JAFP-07-0013, License Renewal Application, Amendment 4, Response to Request for Additional Information2007-01-29029 January 2007 License Renewal Application, Amendment 4, Response to Request for Additional Information ML0704704712007-01-0101 January 2007 Great Lakes St. Lawrence Seaway - Ballast Water ML0704704322007-01-0101 January 2007 Oswego Industrial Directory JAFP-06-0179, JAFNPP - Site Audit Requests - (24) November and December 2006 Monthly Discharge Monitoring Reports2006-12-21021 December 2006 JAFNPP - Site Audit Requests - (24) November and December 2006 Monthly Discharge Monitoring Reports ENOC-06-00018, Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 20062006-08-29029 August 2006 Stations - Fitness-for-Duty Program Performance Report for the Period January 2006 - June 2006 CNRO-2006-00034, Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee2006-07-13013 July 2006 Supplement to Request for Use of Delta Protection Mururoa V4F1 R Supplied Air Suits; Arkansas Nuclear One, Indian Point, Grand Gulf, Waterford, FitzPatrick, River Bend, Pilgrim, Vermont Yankee BVY 06-016, Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 20052006-02-27027 February 2006 Entergy Nuclear Northeast - Fitness-for-Duty Program Performance Report for the Period July 2005 - December 2005 ML0704704112006-01-0101 January 2006 Fws Hydroelectric Licensing BVY 05-089, Entergy Nuclear Northeast - Proof of Financial Protection2005-09-28028 September 2005 Entergy Nuclear Northeast - Proof of Financial Protection ML0636201702005-09-27027 September 2005 JAFNPP Er Ref 8-5 FHA User Guidelines BVY 05-078, Fitness-for-Duty Program Performance Report for the Period January - June 20052005-08-29029 August 2005 Fitness-for-Duty Program Performance Report for the Period January - June 2005 JAFP-05-0126, Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models2005-08-17017 August 2005 Annual Report - Errors in Emergency Core Cooling System (ECCS) Evaluation Models BVY 05-018, Fitness-for-Duty Program Performance Report for the Period July - December 20042005-02-28028 February 2005 Fitness-for-Duty Program Performance Report for the Period July - December 2004 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement JAFP-04-0159, Entergy Nuclear Operations, Inc., NRC Generic Letter 2003-01, Control Room Habitability, Initial Summary Actions Report2004-09-27027 September 2004 Entergy Nuclear Operations, Inc., NRC Generic Letter 2003-01, Control Room Habitability, Initial Summary Actions Report ML0703905852004-09-0101 September 2004 International Joint Commission, 12th Biennial Report Great Lakes Water Quality ML0636201442004-01-31031 January 2004 JAFNPP Er Ref 8-16, DOE Eia Annual Energy Outlook 2004 BVY 03-069, Fitness-for-Duty Program Performance Report for Period January - June 20032003-08-18018 August 2003 Fitness-for-Duty Program Performance Report for Period January - June 2003 ML0701602032003-05-30030 May 2003 JAFNPP - SEIS Web Reference - Mills Et Al 2003 JPN-03-004, Fitness-for-Duty Program Performance Report for the Period July - December 20022003-02-26026 February 2003 Fitness-for-Duty Program Performance Report for the Period July - December 2002 JPN-02-024, Fitness-for-Duty Program Performance Report for the Period January - June 20022002-08-15015 August 2002 Fitness-for-Duty Program Performance Report for the Period January - June 2002 ML0702303602002-08-13013 August 2002 JAFNPP Condition Reports Bird Deaths 2020-10-23
[Table view] |
Text
.j. -Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.James A. Fitzpatrick NPP EntergyP.O.
Box 110 Lycoming, NY 13093 Tel 315-342-3840 JAFP-08-0103 October 2, 2008 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001
Subject:
Entergy Nuclear Operations, Inc.James A. FitzPatrick Nuclear Power Plant License No. DPR-59 Docket No. 50-333 Certificate of Compliance Not Met During Receipt of Low-Level Radioactive Waste Shipment at Barnwell, SC Disposal Facility
Reference:
South Carolina, Department of Health and Environmental Services letter to Mr. John Solowski, Radiation Protection Manager, Entergy Nuclear'Northeast/JAFNPP regarding South Carolina Radioactive Waste Transportation Permit 0031-31-08, dated April 10, 2008
Dear Sir or Madam:
In accordance with 10 CFR 71.95(c), Entergy Nuclear Northeast Operations, Inc., James A. FitzPatrick Nuclear Power Plant (JAF) is providing this report of a discrepancy discovered during receipt of a low level radioactive waste shipment at the disposal facility located in Barnwell, South Carolina.
Following the off-loading of Duratek Transport Cask CNS cask 3-55-1 that originated from JAF, Barnwell personnel determined that the cask base plate lead-in bolt located at the 2 o'clock position was not torqued to 75 ft-lbs., as required by the cask handling procedure referenced in the Certificate of Compliance.
In accordance with 10 CFR 71.95(c), a written report is required within 60 days upon discovery of an event identified in 10 CFR 71.95, paragraphs (a) or (b). JAF's original review of the event determined that the discrepancy was not reportable.
Subsequent review with the NRC concluded that the discrepancy meets reporting criterion 10 CFR 71.95(a)(3) and a late report should be submitted.
Attachment 1 contains the event report.There are no new commitments made in this letter.Should you have any questions or require additional information, please contact Mr.John Solowski, Radiation Protection Manager at (315) 349-6783.L\"5C JAFP-08-0103 Page 2 of 2 Sincerely, Gene Dorman Acting Licensing Manager ED:jm
Attachment:
Event Report cc: Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region I 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Bhalchandra Vaidya, Project Manager Plant Licensing Branch U.S. Nuclear Regulatory Commission Mail Stop 08 C2A Washington, DC 20555 Mr. E. William Brach, Director Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission Mail Stop E3 D2M Washington, DC 20555-0001 Office of NRC Resident Inspector James A. FitzPatrick NPP P.O. Box 136 Lycoming, New York 13093 Mr. Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, New York 10271 Mr. Paul Eddy New York State Department of Public Services 3 Empire State Plaza Albany, New York 12223-1350 Mr. Paul Tonko, President New York State Energy Research and Development Authority 17 Columbia Circle Albany, New York 12203-6399 Mr. Patrick L. Paquin, General Mgr.Energy Solutions 140 Stoneridge Drive Columbia, South Carolina 29210 ATTACHMENT 1 to JAFP-08-0103 James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Event Report ATTACHMENT'1 to JAFP-08-0103
- 1. ABSTRACT: On February 15, 2008, the Barnwell Disposal Facility notified JAF of the discovery of a loose base plate lead-in bolt located at the 2 o'clock position on low-level radioactive waste cask CNS 3-55-1 that was shipped from JAF. The shipment (No. 0208-13587) was classified as Radioactive Material, Type B (U) Package and was transported from JAF on February 12, 2008 as "Exclusive Use". The shipment was transported in accordance with Radioactive Material Quantities of Concern (RAMQC) program requirements.
The shipment contents were irradiated hardware from the JAFspent fuel pool cleanup campaign.
Verbal notification from Barnwell indicated that the loose bolt did not result in a violation of seal integrity, and radiation and contamination surveys had indicated no leakage.On April 10, 2008, JAF received written notification of an infraction from the State of South Carolina (SC), Department of Health and Environmental Control (DHEC), Bureau of Land and Waste Management.
The letter identified the loose bolt discrepancy discovered by Barnwell and noted that the condition was contrary to the requirements of"Handling Procedure For The Duratek Transport Cask CNS 3-55, Certificate of Compliance 5805" and SC Radioactive Material License 097. The letter directed JAF to investigate and institute corrective measures which ensure that all handling procedures involving radioactive material transportation at JAF would be properly implemented and to provide the DHEC documentation of the corrective measures not later than May 12, 2008.2. NARRATIVE:
On February 11, 2008, CNS cask 3-55-1 was prepared by Energy Solutions, Inc. (ES)personnel at the JAF site for shipment of irradiated hardware to the Barnwell Waste Management Facility.
Model CNS 3-55 casks are comprised of a steel-encased, lead-shielded cylindrical body sealed to a base plate by two silicone o-rings and secured by twelve base plate bolts. The base plate bolts were torqued to 75 ft-lbs, as required by the ES cask handling procedure.
Both ES and JAF personnel completed the verification and sign off checklist for the base plate bolt torque values as required by the ES cask handling procedure.
Impact limiters (top and bottom) were also installed and secured to the cask body, each using six impact limiter bolts which were wrench tightened.
ES procedures did not specify a torque value requirement nor independent verification for the installation of the impact limiter bolts.On February 12, 2008, CNS cask 3-55-1 was shipped from JAF to the Barnwell facility.On February 14, 2008, the cask was receipt inspected, surveyed, off loaded from the transport trailer and reloaded to a yard trailer in preparation for the cask to be taken to the slit trench for disposal.
On February 15, 2008, following removal of the impact limiter, a Barnwell technician noted that a base plate lead-in bolt at the 2 o'clock position was loose (less than hand tight). On that same day, JAF was notified of the discovery by the ES Licensing Manager at the Barnwell facility.
During the notification, the ES Licensing Manager reported that there was no violation of cask seal integrity, and-radiation and contamination surveys indicated no leakage.1 of 4 ATTACHMENT 1 to JAFP-08-0103
- 2. NARRATIVE (con't): Status of Components:
Based upon surveys of the shipping cask during the receiving process, the structural integrity of the cask was not affected by the discrepancy.
There was no indication of leakage or shifting of contents.
The discrepancy involved a single closure bolt on the shipping cask. As described in Section 2 of the CNS 3-55 cask safety analysis report, a single loose bolt is within the analyzed design basis of the cask.ii. Dates and approximate times of occurrences:
The discrepancy was discovered on February 15, 2008 at the Barnwell, SC facility.
JAF personnel were notified on that same day by the ES Licensing Manager at the Barnwell facility.iii. Cause of component or system failure: JAF has notified ES, the owner of the cask, of the identified deficiency.
Since JAF does not own the cask or its design basis, we can not definitively determine the cause of the event. Our apparent cause evaluation identified inadequate procedural guidance for installing the impact limiter as a potential cause for the event. Model CNS 3-55 casks are comprised of a cask base plate which is secured to the cask body by twelve base plate bolts and sealed with two silicone o-rings. As part of the installation process, an impact limiter is attached to the cask body after securing the base plate to the cask. The twelve base plate bolts are secured, by procedure, to 75 ft-lbs of torque. The six impact limiter bolts are then wrench tightened to an unspecified torque value. Since the lower impact limiter is secured to the same flange as the cask base plate, compression of the base plate bolting may have occurred upon wrench -tightening of the impact limiter bolts, thereby, causing relief of the base plate bolt during transport.
iv. Failure mechanism:
As noted above, JAF can not definitively determine the failure mechanism.
A potential failure mechanism is wrench tightening of the impact limiter bolts into the same flange as the base plate bolts without specific torque value criteria.
The wrench tightening of the impact limiter bolts might have resulted in compression on the base plate bolting, thereby causing relief of the torque value on a base plate bolt during transport to the Barnwell facility.v. Secondary functions affected: The discrepancy involved a single closure bolt on the shipping cask, and did not affect any secondary functions or components.
vi. Method of discovery:
The discrepancy was discovered during off loading of the liner into the slit trench at the Barnwell, SC facility.2 of 4 t I ATTACHMENT 1 to JAFP-08-0103
- 2. NARRATIVE (con't): vii. Human performance root cause: The event was not primarily the result of human performance deficiencies.
The discrepancy may have been caused by the design of the cask and inadequate ES procedures relating to the installation of the cask impact limiter. ES personnel's failure to incorporate lessons learned from a similar event and JAF's limited initial screening of operating experience within the plant operating experience program were contributing causes.viii. Manufacture/Model number: Shipping Cask No. 3-55-1 and ES Certificate of Compliance No. 5805.ix. Quantities/Content:
Radioactive waste shipment No. 0208-13587 was classified as a Radioactive Material, Type B (U) Package. The shipment contents were irradiated hardware from the JAF spent fuel pool cleanup campaign.3. SAFETY CONSEQUENCES:
There were no direct or likely challenges to nuclear or industrial safety as a result of this event. The discrepancy involved a single closure bolt. Section 2 of the cask'safety analysis report shows that failure of 1 to 3 closure bolts will not result in loss of the cask base plate. Radiological surveys of the shipping cask were conducted at the Barnwell, SC facility upon discovery of the deviation, and no contamination or leakage was detected.4. CORRECTIVE ACTIONS: After performing an apparent cause evaluation, JAF performed the following corrective actions: 0 Notified ES that the CNS 3-55 casks will not be used at JAF until ES determines the cause of the event and implements effective corrective actions to prevent recurrence.
0 Revised JAF's cask handling procedure checklist (RP-OPS-05-07) to include a QA hold point for verification that a second torque check is performed with the cask in the horizontal position.0 Counseled JAF Radiation Protection staff to lower the threshold for entering deviations relating to radioactive waste transport activities into the corrective action program (CAP).3 of 4
.!A 1 4 ATTACHMENT 1 to JAFP-08-0103
- 5. SIMILAR EVENTS: A similar industry event occurred in February, 2007 when Constellation Energy's Nine Mile Point Nuclear Generating Station made a shipment using the same cask.6. CONTACT INFORMATION:
For additional information regarding this event, please contact Mr. John Solowski, Radiation Protection Manager, at 315-349-6783.
- 7. EXPOSURE INFORMATION:
Radiological surveys of the shipping cask were conducted at the Barnwell, SC facility upon discovery of the deviation.
No contamination or leakage were detected, therefore no unexpected radiological exposure to individuals occurred.4 of 4