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MONTHYEARLR-N11-0178, Thirty Day Response to NRC Bulletin 2011-012011-06-0909 June 2011 Thirty Day Response to NRC Bulletin 2011-01 Project stage: Request LR-N11-0207, Sixty Day Response to NRC Bulletin 2011-01, Mitigating Strategies.2011-07-11011 July 2011 Sixty Day Response to NRC Bulletin 2011-01, Mitigating Strategies. Project stage: Request ML1131102482011-11-14014 November 2011 and Salem Nuclear Generating Station, Units 1 and 2 - Request for Additional Information Regarding 60-Day Response to Bulletin 2011-01, Mitigating Strategies Project stage: RAI LR-N11-0363, Response to NRC Bulletin 2011-01, Mitigating Strategies Request for Additional Information2011-12-12012 December 2011 Response to NRC Bulletin 2011-01, Mitigating Strategies Request for Additional Information Project stage: Request ML12220A4602012-08-10010 August 2012 Closeout of Bulletin 2011-01, Mitigating Strategies Project stage: Other ML12220A2502012-08-10010 August 2012 Closeout of Bulletin 2011-01, Mitigating Strategies Project stage: Other 2011-06-09
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Category:Letter type:LR
MONTHYEARLR-N24-0068, Core Operating Limits Report - Cycle 282024-10-21021 October 2024 Core Operating Limits Report - Cycle 28 LR-N24-0063, Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF)2024-10-0707 October 2024 Emergency Plan Document Revision Implemented September 18, 2024. Includes NC.EP-EP.ZZ-0903, Rev. 7, Opening of Emergency Operations Facility (EOF) LR-N24-0059, 2024 Annual 10 CFR 50.46 Report2024-09-30030 September 2024 2024 Annual 10 CFR 50.46 Report LR-N24-0056, Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle2024-09-26026 September 2024 Response to Request for Additional Information Associated with License Amendment Request - Revise Hope Creek Generating Station Technical Specification to Change Surveillance Intervals to Accommodate a 24-Month Fuel Cycle LR-N24-0057, In-Service Inspection Activities2024-09-10010 September 2024 In-Service Inspection Activities LR-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-N24-0027, Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram2024-03-19019 March 2024 Inadvertent Main Turbine Control Valve Closure Caused Reactor Scram 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 2024-09-30
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 JUN 0 9 2011 CPSEG Nuclear LLC 10 CFR 50.54(f)
LR-N11-0178 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, Rockville, MD 20852 Salem Nuclear Generating Station Units 1 and 2 Facility Operating License Nos. DPR-70 and 75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Nuclear Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Thirty Day response to NRC Bulletin 2011-01
Reference:
NRC Bulletin 2011-01, "Mitigating Strategies," dated May 11, 2011 On May 11, 2011, the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2011-01 "Mitigating Strategies". This bulletin requested all holders of operating licenses submit written responses to the Bulletin within 30 and 60 days in accordance with 10 CFR 50.54(f). Enclosure 1 to this letter contains PSEG Nuclear LLC (PSEG) 30 day response.
This letter contains no commitments.
Should you have any questions regarding this transmittal, please contact Mr. Justin Wearne at (856) 339-1351.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on "'Sv fJ e.. '? I 2.0 It Z:;;:::::::?~:;;:::22-~____
Christine Neely Director - Regulatory Affairs
JUN 09 20U Document Control Desk LR-N11-0178 Page 2 cc Mr. W. Dean, Administrator - Region I Mr. R. Ennis, Licensing Project Manager - Salem I Hope Creek USNRC Senior Resident Inspector - Salem (X24)
USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. P. Mulligan, Manager IV - NJBNE Mr. H. Berrick, Salem Commitment Tracking Coordinator Mr. K. Yearwood, Hope Creek Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator
Document Control Desk LR-N11-0178 Enclosure 1 PSEG Nuclear Thirty Day response to NRC Bulletin 2011-01 Question 1 Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
Response
Yes.
In response to the recent events at the Fukushima Daiichi Nuclear Station in Japan, and as part of the overall nuclear industry response to this event, PSEG has performed a verification of the plant's mitigating strategies. This consisted of a thorough inspection that the mitigating strategies equipment is functional, and verification through walkdowns 1 that the mitigating strategies are executable. Letters of Agreement and memorandums of understanding with offsite organizations were re-validated and are all in effect and up-to-date.
The equipment necessary to execute our mitigating strategies is available and capable of performing its intended function in accordance with our current licensing basis.
Question 2 Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?
Response
Yes.
A verification of the skill levels of designated personnel to perform the guidance and strategies was conducted in response to the recent events at Fukushima Daiichi Nuclear Station.
Additionally, a verification that appropriate staffing levels exist to perform the guidance and strategies was completed. Verification through walkdowns 1 that the guidance and strategies are executable was conducted. These walkdowns validated that the guidance and strategies are capable of being executed in our current plant configuration.
The guidance and strategies are capable of being executed given the current configuration of our plants and the current staffing and skill levels of our staff.
1 For the purposes of this document, the term walkdown Includes a table top verification using plant drawings to evaluate mitigating strategies that involve inaccessible plant locations.
Text
PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, NJ 08038-0236 JUN 0 9 2011 CPSEG Nuclear LLC 10 CFR 50.54(f)
LR-N11-0178 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, Rockville, MD 20852 Salem Nuclear Generating Station Units 1 and 2 Facility Operating License Nos. DPR-70 and 75 NRC Docket Nos. 50-272 and 50-311 Hope Creek Nuclear Generating Station Facility Operating License No. NPF-57 NRC Docket No. 50-354
Subject:
Thirty Day response to NRC Bulletin 2011-01
Reference:
NRC Bulletin 2011-01, "Mitigating Strategies," dated May 11, 2011 On May 11, 2011, the Nuclear Regulatory Commission (NRC) issued NRC Bulletin 2011-01 "Mitigating Strategies". This bulletin requested all holders of operating licenses submit written responses to the Bulletin within 30 and 60 days in accordance with 10 CFR 50.54(f). Enclosure 1 to this letter contains PSEG Nuclear LLC (PSEG) 30 day response.
This letter contains no commitments.
Should you have any questions regarding this transmittal, please contact Mr. Justin Wearne at (856) 339-1351.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on "'Sv fJ e.. '? I 2.0 It Z:;;:::::::?~:;;:::22-~____
Christine Neely Director - Regulatory Affairs
JUN 09 20U Document Control Desk LR-N11-0178 Page 2 cc Mr. W. Dean, Administrator - Region I Mr. R. Ennis, Licensing Project Manager - Salem I Hope Creek USNRC Senior Resident Inspector - Salem (X24)
USNRC Senior Resident Inspector - Hope Creek (X24)
Mr. P. Mulligan, Manager IV - NJBNE Mr. H. Berrick, Salem Commitment Tracking Coordinator Mr. K. Yearwood, Hope Creek Commitment Tracking Coordinator Mr. L. Marabella, Corporate Commitment Tracking Coordinator
Document Control Desk LR-N11-0178 Enclosure 1 PSEG Nuclear Thirty Day response to NRC Bulletin 2011-01 Question 1 Is the equipment necessary to execute the mitigating strategies, as described in your submittals to the NRC, available and capable of performing its intended function?
Response
Yes.
In response to the recent events at the Fukushima Daiichi Nuclear Station in Japan, and as part of the overall nuclear industry response to this event, PSEG has performed a verification of the plant's mitigating strategies. This consisted of a thorough inspection that the mitigating strategies equipment is functional, and verification through walkdowns 1 that the mitigating strategies are executable. Letters of Agreement and memorandums of understanding with offsite organizations were re-validated and are all in effect and up-to-date.
The equipment necessary to execute our mitigating strategies is available and capable of performing its intended function in accordance with our current licensing basis.
Question 2 Are the guidance and strategies implemented capable of being executed considering the current configuration of your facility and current staffing and skill levels of the staff?
Response
Yes.
A verification of the skill levels of designated personnel to perform the guidance and strategies was conducted in response to the recent events at Fukushima Daiichi Nuclear Station.
Additionally, a verification that appropriate staffing levels exist to perform the guidance and strategies was completed. Verification through walkdowns 1 that the guidance and strategies are executable was conducted. These walkdowns validated that the guidance and strategies are capable of being executed in our current plant configuration.
The guidance and strategies are capable of being executed given the current configuration of our plants and the current staffing and skill levels of our staff.
1 For the purposes of this document, the term walkdown Includes a table top verification using plant drawings to evaluate mitigating strategies that involve inaccessible plant locations.