Letter Sequence Request |
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MONTHYEARLR-N09-0248, Request for Exemption from Physical Security Requirements2009-11-0303 November 2009
Request for Exemption from Physical Security Requirements
Project stage: Request
LR-N09-0249, Request for Exemption from Physical Security Requirements (Non-Safeguards Version)2009-11-0303 November 2009
Request for Exemption from Physical Security Requirements (Non-Safeguards Version)
Project stage: Request
ML0932000702009-11-12012 November 2009
Email Documenting Conference Call on Part 73 Exemption Requests for Hope Creek and Salem - TACs ME2525, ME2526 and ME2527
Project stage: Other
ML0934405582009-12-10010 December 2009
Notice of Closed Meeting with PSEG Nuclear LLC (PSEG) to Discuss Exemption from Schedular Requirements of 10 CFR 73.55 for Hope Creek Generating Station and Salem Nuclear Generating Station, Unit Nos. 1 and 2
Project stage: Meeting
LR-N09-0314, Request for Scheduler Exemption from Certain Aspects of the New Physical Security Requirements2009-12-22022 December 2009
Request for Scheduler Exemption from Certain Aspects of the New Physical Security Requirements
Project stage: Request
ML0935006442009-12-28028 December 2009
Summary of Closed Meeting with PSEG Nuclear LLC, Regarding Request for Exemption from Schedular Requirements of 10 CFR 73.55 for Hope Creek and Salem Nuclear Generating Station, Unit Nos. 1 and 2 (TAC Nos. ME2525, M2528 and ME2527
Project stage: Meeting
ML1000603672010-01-0606 January 2010
Acceptance Review for TACs ME2525, ME2526 and ME2527 - Hope Creek and Salem 1 and 2 - Exemption from Part 73
Project stage: Acceptance Review
ML1000500392010-01-29029 January 2010
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Environmental Assessment and Finding of No Significant Impact
Project stage: Other
ML1000500542010-01-29029 January 2010
FRN: General Notice. Hope Creek Generating Station & Salem Nuclear Generating Station, Unit Nos. 1 and 2 Environmental Assessment and Finding of No Significant Impact
Project stage: Request
ML1001203072010-02-25025 February 2010
and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Exemption from the Requirements of 10 CFR Part 73, Section 73.55
Project stage: Approval
LR-N10-0171, Stations Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 102010-05-25025 May 2010
Stations Security Plan, Training and Qualification Plan, and Safeguards Contingency Plan, Revision 10
Project stage: Other
2009-12-28
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Category:Letter type:LR
MONTHYEARLR-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
LR-N22-0074, Emergency Plan Evacuation Time Estimate2022-09-15015 September 2022
Emergency Plan Evacuation Time Estimate
LR-N22-0066, License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)2022-08-31031 August 2022
License Amendment Request (LAR) to Relocate Technical Specifications (TS) Requirements for Reactor Head Vents to the Technical Requirements Manual (TRM)
LR-N22-0063, Spent Fuel Cask Registration2022-08-10010 August 2022
Spent Fuel Cask Registration
LR-N22-0068, In-Service Inspection Activities - 90-Day Report2022-08-10010 August 2022
In-Service Inspection Activities - 90-Day Report
LR-N22-0012, License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature2022-08-0707 August 2022
License Amendment Request to Amend the Technical Specifications to Revise and Relocate the Reactor Coolant System Pressure and Temperature Limits and Pressurizer Overpressure Protection System Limits to a Pressure and Temperature
LR-N22-0062, Spent Fuel Cask Registration2022-07-21021 July 2022
Spent Fuel Cask Registration
LR-N22-0006, License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days2022-06-29029 June 2022
License Amendment Request (LAR) to Amend Salem Unit 1 and Unit 2 Technical Specifications (TS) to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days
LR-N22-0051, License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report2022-06-22022 June 2022
License Amendment Request to Relocate Technical Specification Facility/Unit Staff Qualification Requirements to Quality Assurance Topical Report
LR-N22-0044, Emergency Plan Document Revisions Implemented November, 20212022-05-19019 May 2022
Emergency Plan Document Revisions Implemented November, 2021
LR-N22-0043, Core Operating Limits Report - Cycle 292022-05-0909 May 2022
Core Operating Limits Report - Cycle 29
LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr)2022-04-28028 April 2022
2021 Annual Radioactive Effluent Release Report (Rerr)
LR-N22-0040, 2021 Annual Radiological Environmental Operating Report2022-04-28028 April 2022
2021 Annual Radiological Environmental Operating Report
LR-N22-0039, Emergency Plan Document Revisions Implemented March 24, 20222022-04-21021 April 2022
Emergency Plan Document Revisions Implemented March 24, 2022
LR-N21-0052, Request for Relief from ASME Code Defect Removal for Service Water Buried Piping2022-04-0707 April 2022
Request for Relief from ASME Code Defect Removal for Service Water Buried Piping
LR-N22-0023, Guarantees of Payment of Deferred Premiums2022-03-21021 March 2022
Guarantees of Payment of Deferred Premiums
LR-N22-0022, Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds2022-03-21021 March 2022
Response to Request for Additional Information Relief Request S1-14R-210, Alternative Examination of Welds
2023-09-08
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Text
PSEG Nuclear LLC LLC P.O. Box 236 RO. Box 236,,.. Hancocks Hancocks Bridge, NJ 08038-0236 08038-0236 SAFEGUARDS SAFEGUARDS INFORMATION INFORMATION Security Marking Apply Apply Marking Does Not When When This This Letter Is Is OPSEG 0 PSEG Separate from theLetter Enclosure Nuclear L.L. C.
Separate from the Enclosure Nuclear L.L. C.
.NOV 032009 0 3 2009 10 CFR 73.5 LR-N09-0248 LR-N09-0248 Nuclear Regulatory Commission United States Nuclear ATTN: Document Control Control Desk Washington, DC 20555-0001 SALEM GENERATING GENERATING STATION-STATION - UNIT 1 and UNIT 2 OPERATING LICENSE FACILITY OPERATING LICENSE NOS. DPR 70 and DPR-75 DPR-75 NRC DOCKET NOS. 50-272 and 50-311 50-311 GENERATING STATION HOPE CREEK GENERATING STATION OPERATING LICENSE FACILITY OPERATING LICENSE NO. NPF-57 NPF-57 NRC DOCKET NO. 50-354 50-354
Subject:
Subject:
REQUEST FOR FOR EXEMPTION EXEMPTION FROM PHYSICAL SECURITY REQUIREMENTS REQUIREMENTS accordance with the requirements In accordance requirements of 110CFR OCFR 73.5, PSEG Nuclear Nuclear LLC requests the Nuclear Nuclear Regulatory Commission (NRC) approve an exemption from specific requirements of 10 CFR (NRC) approve Part 73, "Physical Protection Protection of Plants and Materials" for the combined combined Salem Salem - Hope Hope Creek Creek extending the deadline for the implementation Generating Station site by extending implementation of certain measures required by the new rule.
The NRC issued a Final Rule for new security requirements requirements in the Federal Register dated March 27, 2009. Pursuant Pursuant to the Final Rule, the new security requirements requirements must bebe implemented implemented by March 31, 31, 2010. PSEG Nuclear has evaluated evaluated these new requirements requirements and determined determined that many of the new requirements requirements can be implemented implemented within this brief implementation implementation period. PSEG Nuclear Nuclear has determined, however, that implementation implementation of specific specific parts of the new requirements requirements will require more more-time involve time to implement since they involve significant significant physical modifications that have a large impact physical modifications impact on the PSEG NuclearNuclear defense defense security security strategy and Protected Area boundary. Therefore, additional time beyond the the 31, 2010 date is requested to complete these security modifications.
March 31,2010 SAFEGUARDS SAFEGUARDS INFORMATION INFORMATION
SAFEGUARDS SAFEGUARDS INFORMATION INFORMATION Document Control Desk 2 LR-N09-0248 LR-N09-0248 PSEG Nuclear Nuclear is requesting the implementation implementation date date be extended from March March 31, 31, 2010 to to December 17, December 17, 2010 for certain new security requirements contained contained in 10 CFR 73.55 as described in the Enclosure described Enclosure to this letter. PSEG Nuclear Nuclear has determined determined that its current security program along with the new security security program requirements that will be implemented security requirements implemented by 31, 2009 will provide continued assurance March 31, assurance of public health health and safety and common common defense defense and security. Accordingly, the requested requested exemption is authorized by law and will not endanger life or property or the common defense defense and security in accordance accordance with 10 CFRCFR 73.5.
Nuclear requests PSEG Nuclear requests approval exemption request by January approval of this exemption January 29, 2010 so that appropriate and timely actions can be taken to revise and implement appropriate implement the PSEG Nuclear Nuclear security security program. The proposed proposed exemptions requested to be effective upon issuance.
exemptions are requested The information provided in the Enclosure to this letter is considered considered Safeguards Safeguards Information Information as described described in 10 CFR 73.21.
73.21. Accordingly, PSEG Nuclear requests that PSEG Nuclear the information thatthe information provided provided in the Enclosure Enclosure be withheld from public disclosure in accordance accordance with 10 CFR 76.21.
76.21.
Non-proprietary/non-safeguards letter (LR-N09-0249)
A second separate Non-proprietary/non-safeguards (LR-N09-0249) accompanying accompanying this this one contains two enclosures, a redacted version of this letter's enclosure the enclosure and the environmental environmental impact statement, both of which are free from proprietary proprietary and safeguards safeguards information and available for public disclosure. .
There are no regulatory regulatory commitments commitments made made in this letter. If If you have any questions or require additional additional information, please do not hesitate hesitate to contact Lee Marabella Marabella at (856) 339-1208 339-1208 or Michelle Patti at (856) 339-3691.
339-3691.
Sincerely, Manager, Licensing
Enclosure:
SAFEGUARDS INFORMATION SAFEGUARDS INFORMATION
SAFEGUARDS SAFEGUARDS INFORMATION INFORMATION Document Control Desk Document 3 LR-N09-0248 LR-N09-0248 C Mr. S. Collins, Administrator - Region I U. S. Nuclear Regulatory Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 19406 Mr. R. Ennis, Project Manager - Salem Unit 1 and Unit 2 Project Manager U. S. Nuclear Regulatory Commission U.
Mail Stop 0881 08B1 Washington, DC 20555-0001 SAFEGUARDS INFORMATION SAFEGUARDS INFORMATION
