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| | issue date = 07/13/2010 | | | issue date = 07/13/2010 |
| | title = Notification of Spent Fuel Cask Registration | | | title = Notification of Spent Fuel Cask Registration |
| | author name = Gaffney M G | | | author name = Gaffney M |
| | author affiliation = PSEG Nuclear, LLC | | | author affiliation = PSEG Nuclear, LLC |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:PSEG Nuclear LLC P.O. Box. 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG Nuclear LLC JUL 1 3 2010 LR-N10-0231 10CFR72.212 ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 Docket Nos. 50-354 and 72-48 PO Box 236 Hancocks Bridge, NJ 08038 | | {{#Wiki_filter:PSEG Nuclear LLC P.O. Box. 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG NuclearLLC JUL 1 3 2010 LR-N10-0231 10CFR72.212 ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 Docket Nos. 50-354 and 72-48 PO Box 236 Hancocks Bridge, NJ 08038 |
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| ==Subject:== | | ==Subject:== |
| Spent Fuel Cask Registration Pursuant to the requirements of IOCFR72.212(b)(1)(ii), PSEG Nuclear LLC (PSEG)hereby reports the following registration information associated with two HI-STORM 100 spent fuel cask systems that were recently placed into storage in the PSEG Independent Spent Fuel Storage Installation (ISFSI).Cask Certificate Cask Model MPC Serial Number Overpack Serial Number Number of Fuel Bundles Placed in Service Cask Certificate Cask Model MPC Serial Number Overpack Serial Number Number of Fuel Bundles Placed in Service 72-1014 Amendment 5 HI-STORM 100 156 202 68 06/21/2010 72-1014 Amendment 5 HI-STORM 100 158 204 68 06/28/2010 There are no regulatory commitments contained in this letter. If you have any questions regarding this submittal, please contact Mr. Timothy Devik, Regulatory Compliance Engineer, at (856) 339-3108.Sincerely, Michael G. (YaffneTSr. | | Spent Fuel Cask Registration Pursuant to the requirements of IOCFR72.212(b)(1)(ii), PSEG Nuclear LLC (PSEG) hereby reports the following registration information associated with two HI-STORM 100 spent fuel cask systems that were recently placed into storage in the PSEG Independent Spent Fuel Storage Installation (ISFSI). |
| Regulatory Assurance Manager -Hope Creek 95-2168 REV. 7/99 Document Control Desk 2 LR-N10-0231 C Mr. W. Dean, Administrator | | Cask Certificate 72-1014 Amendment 5 Cask Model HI-STORM 100 MPC Serial Number 156 Overpack Serial Number 202 Number of Fuel Bundles 68 Placed in Service 06/21/2010 Cask Certificate 72-1014 Amendment 5 Cask Model HI-STORM 100 MPC Serial Number 158 Overpack Serial Number 204 Number of Fuel Bundles 68 Placed in Service 06/28/2010 There are no regulatory commitments contained in this letter. If you have any questions regarding this submittal, please contact Mr. Timothy Devik, Regulatory Compliance Engineer, at (856) 339-3108. |
| -Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager -Hope Creek Mail Stop O8B1A Washington, DC 20555-0001 USNRC Senior Resident Inspector | | Sincerely, Michael G. (YaffneTSr. |
| -Hope Creek (X24)Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 086 HC Commitment Management Coordinator (H02)}} | | Regulatory Assurance Manager - Hope Creek 95-2168 REV. 7/99 |
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| | Document Control Desk 2 LR-N10-0231 C Mr. W. Dean, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager - Hope Creek Mail Stop O8B1A Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24) |
| | Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 086 HC Commitment Management Coordinator (H02)}} |
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Category:Letter type:LR
MONTHYEARLR-N24-0044, Relief Request VR-042024-08-0606 August 2024
Relief Request VR-04
LR-N24-0012, Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding2024-07-24024 July 2024
Application to Revise Technical Specifications and 10 CFR 50.12 Exemption Request to Implement Optimized ZIRLO Fuel Rod Cladding
LR-N24-0030, License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves2024-06-28028 June 2024
License Amendment Request to Revise Technical Specification Lift Settings for Reactor Coolant System Safety/Relief Valves
LR-N24-0041, Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response2024-05-22022 May 2024
Stations, Revisions to Emergency Plan Document Nc EP-EP-ZZ-01102, Rev. 28, Emergency Coordinator Response
LR-N24-0004, License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-05-20020 May 2024
License Amendment Request – Revise Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle
LR-N24-0039, Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage2024-05-0606 May 2024
Steam Generator Tube Inspection Report - Twenty-ninth Refueling Outage
LR-N24-0034, 2023 Annual Radioactive Effluent Release Report (ARERR)2024-04-30030 April 2024
2023 Annual Radioactive Effluent Release Report (ARERR)
LR-N24-0035, 2023 Annual Radiological Environmental Operating Report (AREOR)2024-04-30030 April 2024
2023 Annual Radiological Environmental Operating Report (AREOR)
LR-N24-0024, Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-26026 April 2024
Response to Request for Additional Information Associated with License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
LR-N24-0011, Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary2024-04-0505 April 2024
Supplemental Information to License Amendment Request (LAR) to Modify the Salem and Hope Creek Exclusion Area Boundary
LR-N24-0028, and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal2024-03-28028 March 2024
and Salem Generating Station - Notice of Intent to Pursue Subsequent License Renewal
LR-N24-0021, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2024-03-20020 March 2024
and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums
LR-N24-0020, Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report2024-03-0707 March 2024
Generation Station and Salem Generating Station, Units 1 & 2 - Annual Property Insurance Status Report
LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024
Spent Fuel Cask Registration
LR-N24-0010, Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges2024-02-22022 February 2024
Technical Specification 6.9.1.5.b: 2023 Annual Report of SRV Challenges
LR-N24-0009, In-Service Inspection Activities2024-02-0505 February 2024
In-Service Inspection Activities
LR-N23-0079, Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days2023-12-0707 December 2023
Special Report 23-02-00 Pursuant to the Requirements of Salem Unit 1 Technical Specification 3.3.3.7, Action 10, for the Unit 1 Main Steam Line Rad Monitor Inoperable for Greater than Seven Days
LR-N23-0077, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion2023-11-29029 November 2023
Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2023 & 30 Day Report for Salem Unit 1 Upflow Conversion
LR-N23-0072, Core Operating Limits Report Cycle 302023-11-0101 November 2023
Core Operating Limits Report Cycle 30
LR-N23-0065, Submittal of 2023 Annual 10 CFR 50.46 Report2023-10-0202 October 2023
Submittal of 2023 Annual 10 CFR 50.46 Report
LR-N23-0045, and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement2023-09-0808 September 2023
and Peach Bottom Atomic Power Station, Units 2 and 3 - Notice of Proposed Amendment to Decommissioning Trust Agreement
LR-N23-0055, Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days2023-08-0303 August 2023
Special Report 272/23-01-00, Pursuant to the Requirements of Technical Specification 3.3.3.1, Action 23, for the Vent Noble Gas Rad Monitor Inoperable for Greater than Seven Days
LR-N23-0052, Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.12023-07-31031 July 2023
Retest Schedule for Drywell to Suppression Chamber Vacuum Breakers Per Technical Specification 4.6.2.1
LR-N23-0054, In-Service Inspection Activities2023-07-26026 July 2023
In-Service Inspection Activities
LR-N23-0042, Spent Fuel Cask Registration2023-07-12012 July 2023
Spent Fuel Cask Registration
LR-N23-0046, Emergency Plan Document Revisions Implemented June 28, 20232023-07-10010 July 2023
Emergency Plan Document Revisions Implemented June 28, 2023
LR-N23-0005, License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2023-06-23023 June 2023
License Amendment Request to Amend Technical Specifications (TS) 6.8.4.f for Permanent Extension of Type a and Type C Leak Rate Test Frequencies
LR-N23-0035, 2022 Annual Radioactive Effluent Release Report (ARERR)2023-04-27027 April 2023
2022 Annual Radioactive Effluent Release Report (ARERR)
LR-N23-0034, 2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station2023-04-27027 April 2023
2022 Annual Radiological Environmental Operating Report (AREOR) - Salem Nuclear Generating Station, Unit Nos. 1 and 2 and Hope Creek Generating Station
LR-N23-0033, Core Operating Limits Report Cycle 272023-04-26026 April 2023
Core Operating Limits Report Cycle 27
LR-N23-0010, License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location2023-04-21021 April 2023
License Amendment Request Revision of Technical Specification (TS) to Delete TS Section 5.5 - Meteorological Tower Location
LR-N23-0009, License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains2023-04-18018 April 2023
License Amendment Request (LAR) to Revise the Hope Creek Trip and Standby Auto-start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning (HVAC) Trains
LR-N23-0024, Submittal of Hope Creek Generating Station Technical Specification Bases Changes2023-03-29029 March 2023
Submittal of Hope Creek Generating Station Technical Specification Bases Changes
LR-N23-0006, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-24024 March 2023
Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations
LR-N23-0019, and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums2023-03-21021 March 2023
and Salem Generating Station, Units 1 and 2 - Guarantees of Payment of Deferred Premiums
LR-N23-0016, and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments2023-02-28028 February 2023
and Salem Generating Station, Units 1 and 2 - Report of Changes, Tests, and Experiments
LR-N23-0018, Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges2023-02-27027 February 2023
Technical Specification 6.9.1.5.b - 2022 Annual Report of SRV Challenges
LR-N23-0012, Annual Property Insurance Status Report2023-02-24024 February 2023
Annual Property Insurance Status Report
LR-N23-0014, Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.7172023-02-23023 February 2023
Stations Submittal of 2022 Annual Report of Fitness for Duty Performance Data Per 10 CFR 26.203(e) and 10 CFR 26.717
LR-N23-0003, Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-2112023-02-0101 February 2023
Response to Requests for Additional Information Salem Unit 2 Relief Request S2-I4R-211
LR-N23-0011, In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage2023-01-19019 January 2023
In-Service Inspection Activities - 90 Day Report: Twenty-Fourth Refueling Outage
LR-N22-0096, and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination2023-01-0505 January 2023
and Salem Generating Station, Units 1 and 2 - Request for Threshold Determination
LR-N22-0095, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 20222022-12-20020 December 2022
Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2022
LR-N22-0094, Emergency Plan Document Revisions Implemented November 21, 20222022-12-14014 December 2022
Emergency Plan Document Revisions Implemented November 21, 2022
LR-N22-0092, Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG2022-12-0909 December 2022
Response to Final Iolb Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG
LR-N22-0091, Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments2022-12-0202 December 2022
Independent Spent Fuel Storage Installation, Report of 10 CFR 72.48 Changes, Tests, and Experiments
LR-N22-0084, Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)2022-11-17017 November 2022
Response to Final Request for Additional Information for Salem LAR to Revise TS to Extend Allowed Outage Time for Inoperable EDG (EPID L- 2022-LLA-0095)
LR-N22-0090, Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem2022-11-10010 November 2022
Supplement to Submittal of Salem Generating Station Updated FSAR, Revision 33, 10 CFR 71.106 Review Results and 10 CFR 54.37(b) Review Results for Salem
LR-N22-0075, 2022 Annual 10 CFR 50.46 Report2022-09-30030 September 2022
2022 Annual 10 CFR 50.46 Report
LR-N22-0065, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2022-09-27027 September 2022
Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations
2024-08-06
[Table view] |
Text
PSEG Nuclear LLC P.O. Box. 236, Hancocks Bridge, New Jersey 08038-0236 0 PSEG NuclearLLC JUL 1 3 2010 LR-N10-0231 10CFR72.212 ATTN: Document Control Desk Director, Spent Fuel Project Office Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 Hope Creek Generating Station Facility Operating License No. NPF-57 Docket Nos. 50-354 and 72-48 PO Box 236 Hancocks Bridge, NJ 08038
Subject:
Spent Fuel Cask Registration Pursuant to the requirements of IOCFR72.212(b)(1)(ii), PSEG Nuclear LLC (PSEG) hereby reports the following registration information associated with two HI-STORM 100 spent fuel cask systems that were recently placed into storage in the PSEG Independent Spent Fuel Storage Installation (ISFSI).
Cask Certificate 72-1014 Amendment 5 Cask Model HI-STORM 100 MPC Serial Number 156 Overpack Serial Number 202 Number of Fuel Bundles 68 Placed in Service 06/21/2010 Cask Certificate 72-1014 Amendment 5 Cask Model HI-STORM 100 MPC Serial Number 158 Overpack Serial Number 204 Number of Fuel Bundles 68 Placed in Service 06/28/2010 There are no regulatory commitments contained in this letter. If you have any questions regarding this submittal, please contact Mr. Timothy Devik, Regulatory Compliance Engineer, at (856) 339-3108.
Sincerely, Michael G. (YaffneTSr.
Regulatory Assurance Manager - Hope Creek 95-2168 REV. 7/99
Document Control Desk 2 LR-N10-0231 C Mr. W. Dean, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Mr. R. Ennis, Project Manager - Hope Creek Mail Stop O8B1A Washington, DC 20555-0001 USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. P. Mulligan, Manager IV Bureau of Nuclear Engineering PO Box 415 Trenton, New Jersey 086 HC Commitment Management Coordinator (H02)
