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Category:Letter
MONTHYEARIR 05000261/20230042024-01-31031 January 2024
Integrated Inspection Report 05000261/2023004
ML24009A2432024-01-25025 January 2024
Unit, No. 2 - Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0047 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting))
ML24009A2712024-01-24024 January 2024
Revision to Reactor Vessel Material Surveillance Capsule Withdrawal Schedule
ML23354A0052024-01-0808 January 2024
Request for Withholding Information from Public Disclosure, H. B. Robinson Steam Electric Plant, Unit No. 2
ML23342A0902023-12-0808 December 2023
Notification of Inspection and Request for Information for NRC Problem Identification and Resolution Inspection
IR 05000261/20234202023-11-30030 November 2023
Security Baseline Inspection Report 05000261/2023420 (Cover Letter with Report)
IR 05000261/20230102023-11-28028 November 2023
Fire Protection Team Inspection Report 05000261/2023010
ML23317A3462023-11-14014 November 2023
Duke Fleet - Correction Letter to License Amendment Nos. 312 & 340 Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML23293A2992023-11-0808 November 2023
Amendment No. 18 to Certificate of Compliance No. 1004 for the Standardized NUHOMS System (Docket No. 72-1004, CAC No. 001028, (Enterprise Project Identifier: L-2022-LLA-0079)
IR 05000261/20230032023-11-0707 November 2023
Integrated Inspection Report 05000261 2023003 and 07200060 2023001
ML23226A0862023-10-12012 October 2023
Issuance of Amendment No. 277 Regarding Revision of TSs to Add High-High Steam Generator Level Function to Table 3.3.2-1 and Remove Obsolete Content from TSs 2.1.1.1 and 5.6.5.b
ML23284A0642023-10-11011 October 2023
Supplement to Submittal of Biennial Reports of 72.48 Evaluations Performed for the Standardized NUHOMS System, Certificate of Compliance (CoC) 1004, for the Periods 07/26/2016 to 07/25/2018 and 7/28/2020 to 7/27/2022, Docket 72-1004
ML23346A1322023-10-0606 October 2023
Communication from C-10 Research & Education Foundation Regarding NextEra Common Emergency Fleet Plan License Amendment Request and Related Documents Subsequently Published
ML23206A0172023-09-29029 September 2023
Congressional Letters: List of Approved Spent Fuel Storage Casks: Tn Americas LLC Standardized NUHOMS Horizontal Modular Storage System, Certificate of Compliance No. 1004, Renewed Amendment No.18
ML23256A0882023-09-25025 September 2023
Issuance of Alternative to Steam Generator Welds
ML23195A0782023-08-29029 August 2023
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-554, Revision 1
ML23235A0552023-08-23023 August 2023
Notification of an Fire Protection Team Inspection (FPTI) (NRC Inspection Report 05000261/2023010) and Request for Information (RFI)
IR 05000261/20230052023-08-21021 August 2023
Updated Inspection Plan for H.B. Robinson Steam Electric Plant (Report 05000261/2023005)
IR 05000261/20230022023-08-0707 August 2023
Integrated Inspection Report 05000261/2023002
IR 05000261/20234022023-05-30030 May 2023
Cyber Security Inspection Report 05000261/2023402
ML23145A1602023-05-25025 May 2023
Submittal of Updated Final Safety Analysis Report (Revision No. 30), Independent Spent Fuel Storage Installation Safety Analysis Report (Revision No. 28), Technical Specifications Bases Revisions, Quality
IR 05000261/20230012023-05-0202 May 2023
Integrated Inspection Report 05000261/2023001
ML23118A0762023-05-0101 May 2023
Approval for Use of Specific Provision of a Later Edition of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI
ML23095A1012023-04-0505 April 2023
Tn Americas LLC, Third Supplemental Response to Request for Additional Information Application for Amendment 18 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks, Revision 6
ML22332A4932023-03-10010 March 2023
William States Lee III 1 and 2 - Issuance of Amendments Regarding the Relocation of the Emergency Operations Facility
ML23067A0772023-03-0808 March 2023
Tn Americas LLC, Second Supplemental Response to Request for Additional Information for Amendment 18 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks Non-Proprietary
IR 05000261/20220062023-03-0101 March 2023
Annual Assessment Letter for H.B. Robinson Steam Electric Plant, Unit 2 (Report 05000261/2022006)
ML23047A4512023-02-21021 February 2023
Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000261/2023402
ML23047A0282023-02-16016 February 2023
Supplemental Response to Request for Additional Information - Application for Amendment 18 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks, Revision 4 (Docket No. 72-1004, CAC No. 001028, EPID: L-2022-
ML23041A2272023-02-13013 February 2023
2022 Q4 Robinson_Workflow Final
ML23030A6682023-01-30030 January 2023
Independent Spent Fuel Storage Installation ((Isfsi) - Submittal of Cask Registration for Spent Fuel Storage
ML23027A0562023-01-27027 January 2023
Response to Request for Additional Information Application for Amendment 18 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks, Revision 3 (Docket No. 72-1004, CAC No. 001028, EPID: L-2022-LLA-0079)
ML23020A9212023-01-20020 January 2023
Amendment 18 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks Request for Additional Information Non-Proprietary Responses
ML22329A2982023-01-19019 January 2023
Issuance of Amendment No. 274 Regarding Revision of Technical Specification 3.8.1 Surveillance Requirement 3.8.1.16
ML22355A0932023-01-0606 January 2023
Orano Tn Americas - USNRC Inspection Report 72-1004/2022-203
ML23005A1712023-01-0404 January 2023
Independent Spent Fuel Storage Installation (Isfsi), Submittal of Cask Registration for Spent Fuel Storage
ML22313A0462022-12-21021 December 2022
Letter-Review of Amd18 CoC No. 1004 Request for Additional Information
ML22294A0922022-12-15015 December 2022
Issuance of Amendment No. 273 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections, Revision 1
ML22339A1362022-12-0101 December 2022
2023 Requalification Program Inspection - H.B. Robinson Nuclear Plant
ML22322A1322022-11-18018 November 2022
301, NRC Operator License Examination Report & Cover Letter Merged
ML22096A0032022-11-18018 November 2022
McGuire Nuclear Station and Shearon Harris Nuclear Power Plant Authorization of RA-19-0352 Regarding Use of Alternative for RPV Head Closure Stud Examinations
ML22256A2532022-11-14014 November 2022
Issuance of Amendments Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-541, Rev. 2
IR 05000261/20220032022-11-0303 November 2022
Integrated Inspection Report 05000261 2022003
IR 05000261/20224022022-10-19019 October 2022
Security Baseline Inspection Report 05000261/2022402
IR 05000261/20220102022-09-26026 September 2022
Design Basis Assurance Inspection (Teams) Inspection Report 05000261/2022010
IR 05000261/20223012022-09-23023 September 2022
301 Operator License Exam Approval Letter (05000261/2022301)
ML22258A0302022-09-15015 September 2022
Evacuation Time Estimate Reports
ML22231B1362022-09-0101 September 2022
Review of the Draft Environmental Assessment and Findings of No Significant Impact for Catawba Nuclear Station, H.B. Robinson Steam Electric Plant, and Oconee Nuclear Station Independent Spent Fuel Storage Installation Decommissioning Fundi
IR 05000261/20220052022-08-26026 August 2022
Updated Inspection Plan for the H.B Robinson Steam Electric Plant - Report 05000261/2022005-Final
ML22224A0412022-08-12012 August 2022
Tn Americas, LLC, Submittal of Response to Request for Supplemental Information - Application for Amendment 18 to Standardized NUHOMS Certificate of Compliance No. 1004 for Spent Fuel Storage Casks, Revision 1
2024-01-08
[Table view]
Category:Licensee 30-Day Written Event Report
MONTHYEARL-MT-16-050, Thirty-Day Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel2016-10-20020 October 2016
Thirty-Day Notification for Dry Shielded Canister MNP-61 BTH-1-B-2-016 Pursuant to 10 CFR 72.212, Conditions of General License Issued Under 10 CFR 72.210, for the Storage of Spent Fuel
ML16239A0712016-08-25025 August 2016
ISFSI - Thirty-Day Report for Engagement of Active Cooling for OS197 Fc Transfer Cask During Transfer of a Loaded Dry Shielded Canister
NLS2014055, ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 for Storage of Spent Fuel2014-06-24024 June 2014
ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 for Storage of Spent Fuel
NLS2011009, ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 for Storage of Spent Fuel2011-01-19019 January 2011
ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 for Storage of Spent Fuel
NLS2011001, Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions If General License Issued Under Section 72.210, for Storage of Spent Fuel2011-01-0505 January 2011
Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions If General License Issued Under Section 72.210, for Storage of Spent Fuel
NLS2010109, ISFSI, Thirty-Day Notification Pursuant to 10 CFR 72.212, for Storage of Spent Fuel2010-12-14014 December 2010
ISFSI, Thirty-Day Notification Pursuant to 10 CFR 72.212, for Storage of Spent Fuel
NLS2010099, ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212 for Storage of Spent Fuel2010-11-15015 November 2010
ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212 for Storage of Spent Fuel
ML0823208842008-08-13013 August 2008
Site, Independent Spent Fuel Storage Instillation (ISFSI) General License Cask Certificate of Compliance, 30-Day Report Due to Higher Canister Heat Loading
2016-08-25
[Table view] |
Text
David S. Hoffman H. B. Robinson Steam Electric Plant Unit 2 Director - Nuclear Org Effectiveness Duke Energy Progress 3581 West Entrance Road Hartsville, SC 29550 0 . 843 857 5239 F: 843 857 1319 David.hoffman@duke-energy.com 10 CFR 72.238 Serial: RNP-RN16-0068 AUG 2 5 2016 Document Control Desk Director, Division of Spent Fuel Storage and Transportation Office of Nuclear Material Safety and Safeguards United States Nuclear Regulatory Commission Washington, DC 20555-0001 H. 8. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261/RENEWED LICENSE NO. DPR-23 INDEPENDENT SPENT FUEL STORAGE INSTALLATION DOCKET NO. 72-60 THIRTY (30) DAY REPORT FOR ENGAGEMENT OF ACTIVE COOLING FOR 05197 FC TRANSFER CASK DURING TRANSFER OF A LOADED DRY SHIELDED CANISTER Ladies and Gentlemen:
Pursuant to 10 CFR 72.238, Certificate of Compliance (CoC) 1004, Amendment Number 13, Article 3.d.5, and Technical Specification 3.1.3 (TS 3.1.3), Duke Energy Progress, hereby provides the following information to comply with the requirement to submit a 30 day report, for engagement of active cooling for the OS 197 FC Transfer Cask during transfer of a loaded Dry Shielded Canister (DSC), into the Horizontal Storage Module (HSM) on the Independent Spent Fuel Storage Installation (ISFSI) at the H. 8. Robinson Steam Electric Plant (HBRSEP), Unit No.
2, dated July 28, 2016. It is noted, HBRSEP remained compliant with the requirements and the expectation of TS 3.1 .3, Updated Final Safety Analysis Report (UFSAR) and governing procedures throughout the entire operational evolution.
A narrative describing major occurrences during the evolution, detailed information related to the cask, key actions, and evaluations and analyses supporting the basis for the conclusion of no adverse impact to the health and safety of the public follows.
United States Nuclear Regulatory Commission Serial: RNP-RA/16-0068 Page 2 of 3 Cask Information:
Licensee Name: Duke Energy Progress Licensee Address: H. 8 . Robinson Steam Electric Plant (HBRSEP), Unit No. 2 3581 West Entrance Road Hartsville, SC 29550 Reactor License Number: DPR-23 Reactor Docket Number: 50-261 ISFSI Docket Number: 72-1004 Information
Contact:
Tony Pilo, Manager (Acting) - Nuclear Regulatory Affairs 843-857-1409.
Cask Certificate Number: 1004, Amendment 13 Cask Model Number: NUHOMS- 24PTH-L-1C-HZ19 Date Placed in Service 07/29/2016 Horizontal Storage HSM27 Module Number Heat Load (kW) 26.51 While attempting to insert DSC RNP-24PTH-L-1C-HZ19 (DSC HZ19) into HSM 27 on July 28, 2016, the DSC stalled and was unable to be inserted. DSC HZ19 is a type 1C basket with heat load zone 1 fuel and a decay heat load of 26.51 kW per the fuel selection package. Per CoC 1004 Amendment 13 Technical Specification (TS) 3.1.3, DSC HZ19 had a 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> limit from beginning of annulus draining to full insertion of the DSC into the HSM. After consulting with AREVA TN engineering and before the 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> time limit expired, partially inserted DSC HZ19 was retracted from the HSM back into the transfer cask (TC) and forced air cooling was started on diesel generators within the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limit in TS 3.1 .3 condition A2. While retracting DSC HZ19, it was noted that the digital distance readout on the non-safety related hydraulic power unit (HPU) was showing a negative number when a positive or zero number was expected. As DSC HZ19 was retracted, the DSC shell, TC lip, and HSM rails were visually inspected but no damage or wear was noted. A backup HPU was rented from AREVA TN in the event the utility-owned HPU was unable to be fixed but was not used.
After troubleshooting, it was discovered that the hydraulic ram that is supplied by the HPU, was stalling out between the 3 stages of the ram where the diameter of the ram becomes smaller.
Some set-points in the HPU software that calculate ttie distance that the ram is extended were adjusted with AREVA TN guidance such that the HPU would produce the correct needed pressure for the ram at the specified distance. No other systems or components were affected.
United States Nuclear Regulatory Commission Serial: RNP-RN16-0068 Page 3 of 3 AREVA TN engineering provided a calculation that allowed a minimum forced air cooling time of 30 minutes to reset the conditions of TS 3.1.3 such that the 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> insertion time limit was restarted when forced air cooling was stopped. This 30 minute limit was based conservatively on basket type and total decay heat load. After being on forced air cooling for approximately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />, forced air cooling was stopped, and DSC HZ19 was successfully inserted into HSM 27 on July 29, 2016.
Additional troubleshooting following the insertion of DSC HZ 19, AREVA TN discovered an error in the calculation software of the HPU as the cause of the issue. The calculation and set-points are part of the manufacturer's controlled settings on the HPU. AREVA TN representative corrected the calculation in the software. This issue was not caused by human performance, lack of training, bad or incorrect communications, lack of oversight, or lack of maintenance during insertion of DSC HZ 19. The HPU was successfully used in subsequent DSC insertions.
During the entirety of the evolution, no TS, UFSAR, or procedure steps or limits were violated.
Although the 9.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> insertion time limit was not met, forced air cooling was started within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and maintained per TS 3.1.3 condition A2 without interruption until the minimum 30 minute run time required was met per AREVA TN calculation 11165-0400, dated July 29, 2016.
This AREVA TN calculation shows that even without forced air cooling, fuel and TC integrity were not challenged and the health and safety of the public was not adversely impacted.
Sincerely, David S. Hoffman Director - Nuclear Organization Effectiveness DSH/am cc: NRC Regional Administrator, NRC, Region II Mr. Robert Carrion, NRC, Region II, ISFSI Coordinator NRC Resident Inspector, HBRSEP, Unit No. 2 Mr. Dennis Galvin, NRC Project Manager, NRR
