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MONTHYEARLR-N09-0264, Request for Approval of Cyber Security Plan2009-11-23023 November 2009 Request for Approval of Cyber Security Plan Project stage: Request LR-N10-0235, Request for Approval of Salem-Hope Creek Cyber Security Plan2010-07-14014 July 2010 Request for Approval of Salem-Hope Creek Cyber Security Plan Project stage: Request ML1020804472010-08-0404 August 2010 Withdrawal of License Amendment Request Regarding Cyber Security Plan Project stage: Withdrawal ML1021702922010-08-0505 August 2010 Acceptance Review for TACs ME4352, ME4353 and ME4354 - Hope Creek and Salem 1 and 2 - License Amendment Request Regarding Cyber Security Plan Project stage: Acceptance Review LR-N10-0354, Stations - Notification Letter Designating Balance of Plant Systems within the Cyber Security Rule Scope2010-09-28028 September 2010 Stations - Notification Letter Designating Balance of Plant Systems within the Cyber Security Rule Scope Project stage: Request ML1105507682011-03-0202 March 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Request for Additional Information Regarding License Amendment Request for Approval of Cyber Security Plan Project stage: RAI LR-N11-0079, Response to Request for Additional Information for Approval of the Salem-Hope Creek Cyber Security Plan2011-04-0101 April 2011 Response to Request for Additional Information for Approval of the Salem-Hope Creek Cyber Security Plan Project stage: Response to RAI LR-N11-0159, Request for Approval of the Salem-Hope Creek Cyber Security Plan2011-06-28028 June 2011 Request for Approval of the Salem-Hope Creek Cyber Security Plan Project stage: Request LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011 Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal Project stage: Supplement ML1118615602011-07-28028 July 2011 and Salem Nuclear Generating Station, Unit Nos. 1 and 2, License Amendment, Issuance of Amendments Approval of Cyber Security Plan Project stage: Approval ML11291A0592011-10-0707 October 2011 End-of-Cycle 20 Steam Generator Tube Inspection Report Project stage: Request ML1207600342012-03-29029 March 2012 Request for Additional Information Regarding Steam Generator Tube Inservice Inspection Report for End of Cycle 20 Project stage: RAI ML12130A2612012-05-0101 May 2012 Response to Request for Additional Information Regarding Steam Generator Tube Inservice Inspection Report for End of Cycle 20 Project stage: Response to RAI ML12151A3592012-06-0707 June 2012 End of Cycle 20 Steam Generator Tube Inservice Inspection Report Review Project stage: Other 2011-03-02
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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
[Table view] Category:Technical Specifications
MONTHYEARML23341A1372024-01-16016 January 2024 Issuance of Amendment No. 235 Revise Trip and Standby Auto-Start Logic Associated with Safety Related Heating, Ventilation and Air Conditioning ML23192A8212023-08-14014 August 2023 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 234, 347, and 329 Revise Technical Specifications to Delete Meteorological Tower Location 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 ML21295A2292021-11-15015 November 2021 Issuance of Amendment Nos. 340 and 321 Revise Technical Specifications to Adopt TSTF 569, Revision of Response Time Testing Definitions ML21050A0022021-03-12012 March 2021 Issuance of Amendment No. 227 Revise Technical Specifications to Adopt Technical Specifications Task Force Traveler TSTF-582, RPV WIC Enhancements ML21047A3132021-03-10010 March 2021 Issuance of Amendment No. 226 Revise Emergency Core Cooling System Technical Specification for High Pressure Coolant Injection System Inoperability (Non-Proprietary) ML20281A6132020-11-0909 November 2020 Issuance of Amendment No. 225 Revise Technical Specification Actions for Suppression Pool Cooling ML20231A6322020-09-29029 September 2020 Issuance of Amendment No. 224 Regarding Adoption of 10 CFR 50.69, Risk Informed Categorization and Treatment of Structures, Systems and Components of Nuclear Power Reactors ML20034E6172020-02-27027 February 2020 and Salem Nuclear Generating Station, Unit Nos. 1 and 2 - Issuance of Amendment Nos. 222, 333, and 314 Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions and License Transfer ML19275D6942019-11-18018 November 2019 Issuance of Amendment Nos. 330 and 311 Revise Technical Specifications to Adopt TSFT-547, Clarification of Rod Position Requirements ML19186A2052019-08-0606 August 2019 Issuance of Amendment No. 217 Remote Shutdown System ML19065A1562019-03-27027 March 2019 Issuance of Amendment No. 215 Inverter Allowed Outage Time Extension LR-N18-0129, License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements.2019-02-0404 February 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-547, Clarification of Rod Position Requirements. ML17317A6052017-12-13013 December 2017 Issuance of Amendment, License Amendment Request to Adopt Technical Specifications Task Force (TSTF) Traveler TSTF-535 ML17047A0202017-03-21021 March 2017 Issuance of Amendment to Delete Technical Specification Action Statement 3.4.2.1.b Associated with Stuck Open Safety/Relief Valves ML17053A1782017-03-15015 March 2017 Issuance of Amendment to Permit Operability of Low Pressure Coolant Injection While Aligned to Shutdown Cooling ML16270A0382016-10-13013 October 2016 Issuance of Amendment No. 200 Safety Limit Minimum Critical Power Ratio Change ML16096A4192016-04-28028 April 2016 Issuance of Amendments Replacement of Source Range and Intermediate Range Neutron Monitoring Systems ML16054A0682016-03-28028 March 2016 Issuance of Amendments Regarding Revision to Reactor Trip System Instrumentation Technical Specifications ML16035A0872016-03-0707 March 2016 Issuance of Amendments New Technical Specifications to Isolate Unborated Water Sources in Mode 6 LR-N16-0044, Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel2016-02-11011 February 2016 Emergency License Amendment Request to Modify Technical Specification Requirements for One Inoperable Subcooling Margin Monitor Channel ML15286A0912015-11-30030 November 2015 Issuance of Amendment Adoption of Technical Specifications Task Force Traveler-522 LR-N15-0224, Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling)2015-11-25025 November 2015 Response to Request for Additional Information License Amendment Request to Isolate Unborated Water Sources and Use Gamma-Metrics Post-Accident Neutron Monitors During Mode 6 (Refueling) LR-N15-0182, License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements2015-10-12012 October 2015 License Amendment Request to Correct a Non-Conservative Technical Specification Applicability Statement and Inconsistent Action Statements ML15245A6362015-09-0404 September 2015 Issuance of Emergency Amendment Regarding Removal of Pressurizer Power Operated Relief Valve Position Indication Instrumentation from Technical Specifications ML15153A2302015-07-30030 July 2015 Issuance of Amendments Adopting Technical Specification Task Force (TSTF)-510, Rev, 2, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection(Tac Nos. MF4574 & MF457 ML15141A2712015-06-17017 June 2015 and Salem Nuclear Generating Station, Unit Nos.1 and 2, Issuance of Amendments Update of Appendix B to the Renewed Facility Operating Licenses ML15063A2932015-03-30030 March 2015 Issuance of Amendments Revision to Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor ML14108A3992014-12-18018 December 2014 Issuance of Amendment Request to Relocate Flood Protection Technical Specification to the Technical Requirements Manual LR-N14-0189, License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process2014-11-25025 November 2014 License Amendment Request to Revise Technical Specifications to Adopt TSTF-522, Revision 0, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month Using the Consolidated Line Item Improvement Process ML14108A3122014-07-29029 July 2014 Issuance of Amendment Request to Relocate Safety Relief Valve Position Instrumentation to Technical Requirements Manual LR-N14-0074, License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor2014-03-24024 March 2014 License Amendment Request to Revise Power Distribution Limits for Axial Flux Difference and Heat Flux Hot Channel Factor LR-N13-0155, License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual2013-09-0505 September 2013 License Amendment Request to Relocate the Flood Protection Technical Specification to the Technical Requirements Manual LR-N13-0143, License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual2013-07-30030 July 2013 License Amendment Request to Relocate Safety/Relief Valve Position Instrumentation to the Technical Requirements Manual LR-N12-0183, License Amendment Request: Revision to Technical Specification (TS) 3.7.6.1 (Unit 1) and 3.7.6 (Unit 2) Control Room Emergency Air Conditioning System2012-07-17017 July 2012 License Amendment Request: Revision to Technical Specification (TS) 3.7.6.1 (Unit 1) and 3.7.6 (Unit 2) Control Room Emergency Air Conditioning System LR-N12-0067, License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items2012-03-0101 March 2012 License Amendment Request to Correct Technical Specification and Facility Operating License Editorial Items LR-N12-0028, Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process2012-01-26026 January 2012 Supplement to Application for Tech Spec Change TSTF-477 Rev. 3, Add Action for Two Inoperable Control Room AC Subsystems to the Tech Specs Using Consolidated Line Item Improvement Process ML11116A1482011-07-20020 July 2011 Issuance of Renewed Facility Operating License No. NPF-57 for Hope Creek Generating Station ML0527202982011-07-20020 July 2011 Current Facility Operating License NPF-57, Tech Specs, Revised 12/18/2017 LR-N11-0208, Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal2011-07-0606 July 2011 Revised License Condition- Salem-Hope Creek Cyber Security Plan Supplement Submittal ML11175A2072011-06-30030 June 2011 Appendices a, B and C ML11136A0642011-06-30030 June 2011 Issuance of Renewed Facility Operating License Nos. DPR-70 and DPR-75 for Salem Nuclear Generating Station, Units 1 and 2 ML1109801512011-04-19019 April 2011 Correction to Amendment No. 187 Regarding Relocation of Specific Surveillance Frequencies to a Licensee-Controlled Program Based on Technical Specification Task Force (TSTF) Change TSTF-425 LR-N11-0098, Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 1872011-04-0404 April 2011 Format and Editorial Corrections to Technical Specification Pages Issued with Amendment 187 LR-N11-0068, Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process2011-02-28028 February 2011 Application for Technical Specification Change TSTF-477, Revision 3, Add Action for Two Inoperable Control Room AC Subsystems to the Technical Specifications Using Consolidated Line Item Improvement Process LR-N10-0363, License Amendment Request: Changes to Snubber Surveillance Requirements2010-10-0404 October 2010 License Amendment Request: Changes to Snubber Surveillance Requirements ML1020805012010-08-20020 August 2010 License Amendment, Issuance of Amendments Surveillance Requirements for Inservice Inspection and Inservice Testing LR-N10-0310, Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times.2010-08-19019 August 2010 Supplement to License Amendment Request H09-06 to Adopt TSTF-460, Rev. 0, Control Rod Scram Times. ML1015907132010-07-21021 July 2010 Issuance of Amendment Control Rod Notch Testing Frequency LR-N10-0098, License Amendment Request - One Time On-Line Safety-Related Battery Replacement2010-03-29029 March 2010 License Amendment Request - One Time On-Line Safety-Related Battery Replacement 2024-01-16
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PSEG p.o. Box 236, Hancocks Bridge, NJ 08038-0236 OPSEG Nuclear LLC JUL 06 2011 LR-N 11-0208 10CFR 50.90 LAR H09-07 10CFR 50.4 LAR S09-08 United States Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 SALEM GENERATING STATION - UNIT 1 and UNIT 2 RENEWED FACILITY OPERATING LICENSE NOS. DPR-70 and DPR-75 NRC DOCKET NOS. 50-272 and 50-311 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NO. NPF-57 NRC DOCKET NO. 50-354
Subject:
REVISED LICENSE CONDITION - SALEM-HOPE CREEK CYBER SECURITY PLAN SUPPLEMENT SUBMITTAL
References:
(1) Letter LR-N11-0159, Robert Braun to US NRC Document Control Desk, "REQUEST FOR APPROVAL OF THE SALEM-HOPE CREEK CYBER SECURITY PLAN", dated June 6, 2011.
(2) E-mail from Richard B. Ennis, (U.S. Nuclear Regulatory Commission) to Paul Duke, "Supplement Needed for Revised License Condition - Salem-Hope Creek Cyber Security Plan", dated June 29, 2011.
In reference 1, in accordance with the provisions of 10 CFR 50.4 and 10 CFR 50.90, PSEG Nuclear, LLC (PSEG) proposed a revision to the existing FOL Physical Protection license condition to require PSEG to fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan. Subsequent to that submittal, the NRC staff provided PSEG with proposed minor modifications (reference
- 2) to the license condition proposed by PSEG in reference 1 for the Cyber Security Plan amendment requests.
Document Control Desk LR-N11-0208 In accordance with the provisions of 10 CFR 50.4 and 50.90, PSEG submits this revised request for an amendment to the Facility Operating Licenses (FOL) for Salem Nuclear Generating Station Unit 1 and Unit 2 and Hope Creek Generating Station. This proposed amendment provides replacement pages which contain the exact wording proposed by the NRC staff in reference 2. The enclosed attachment provides revised marked up pages to the Salem Units 1 and 2 and Hope Creek Facility Operating License (FOL) Physical Protection license condition.
There are no additional commitments contained within this letter.
In accordance with 10 CFR 50.91, a copy of this letter is being provided to the designated State Officials. If you have any questions or require additional information, please contact Mr. Lee Marabella at (856) 339-1208.
I declare under penalty of perjury that the foregoing is true and correct.
Date: 7/U'/"
Robert Braun Senior Vice President - Nuclear Attachment - Revised marked up pages to the Salem Units 1 and 2 and Hope Creek Facility Operating License (FOL)
C: - Administrator - Region I - U. S. Nuclear Regulatory Commission
- U. S. Nuclear Regulatory Commission Project Manager - Salem Unit 1 and Unit 2 and Hope Creek
- USNRC Senior Resident Inspector - Hope Creek Generating Station
- USNRC Senior Resident Inspector - Salem Generating Station
- Manager IV - N.J. Bureau of Nuclear Engineering
- Corporate Commitment Tracking Coordinator
- Commitment Coordinator - Salem
- Commitment Coordinator - Hope Creek 2
Attachment LR-N 11-0208 ATTACHMENT License Amendment Request Salem Generating Station Units 1 & 2 NRC Docket Nos. 50-272 and 50-311 And Hope Creek Generating Station NRC Docket No. 50-354 Salem-Hope Creek Cyber Security Plan Proposed Technical Specification Changes (Mark-ups) 1
Attachment LR-N11-0208 MARKED UP TECHNICAL SPECIFICATION PAGES Salem Generating Station, Unit 1 Renewed Facility Operating License Page 9
2
evaluates such changes pursuant to the criteria set forth in 10 CFR 50.59 and otherwise complies with the requirements in that section.
(19) Appendix A of NUREG-21 01, "Safety Evaluation Report Related to the License Renewal of Salem Nuclear Generating Station," dated June 2011, and PSEG Nuclear LLC UFSAR supplement submitted pursuant to 10 CFR 54.21(d), as revised on May 18, 2011, describe certain future programs and activities to be completed before the period of extended operation. PSEG Nuclear LLC shall complete these activities no later than August 13, 2016, and shall notify the NRC in writing when implementation of these activities is complete.
(20) All capsules in the reactor vessel that are removed and tested must meet the test procedures and reporting requirements of American Society for Testing and Materials (ASTM) E 185-82 to the extent practicable for the configuration of the specimens in the capsule. Any changes to the capsule withdrawal schedule, including spare capsules, must be approved by the NRC prior to implementation.
All capsules placed in storage must be maintained for future insertion. Any changes to storage requirements must be approved by the NRC. Changes to the withdrawal schedule or storage requirements shall be submitted to the NRC as a report in accordance with 10 CFR 50.4.
(21) PSEG Nuclear LLC shall take one core sample in the Unit 1 spent fuel pool west wall, by the end of 2013, and one core sample in the east wall where there have been indications of borated water ingress through the concrete, by the end of 2015. The core samples (east and west walls) will expose the rebar, which will be examined for signs of corrosion. Any sample showing signs of concrete degradation and/or rebar corrosion will be entered into the licensee's corrective action program for further evaluation. PSEG Nuclear LLC shall submit a report in accordance with 10 CFR 50.4 no later than three months after each sample is taken on the results, recommendations, and any additional planned actions.
D. Paragraph 2.0. has been combined with paragraph 2.E. per Amendment No. 86, June 27, 1988.
E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).
The plans, submitted by letter dated May 19, 2006, are entitled: "Salem-Hope Creek Nuclear Generating Station Security Plan," "Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan," and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan." The plans contain Safeguards Information protected under 10 CFR 73.21.
PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), Renewed License No. DPR-70 including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.S4(p). The Salem-Hope Creek CSP was approved by License Amendment No. xxx.
Attachment LR-N11-0208 MARKED UP TECHNICAL SPECIFICATION PAGES Salem Generating Station, Unit 2 Renewed Facility Operating License Page 11 3
issuance of the License for Fuel-Loading and Low-Power Testing, dated April 18, 1980.
The facility will operate, to the extent authorized herein, in conformity with the application as amended, the provisions of the Act, and the regulations of the Commission.
E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54 (p).
The plans, submitted by letter dated May 19, 2006, are entitled: "Salem-Hope Creek Nuclear Generating Station Security Plan," "Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan," and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan." The plans Contain Safeguards Information protected under 10 CFR 73.21.
F. A tem orary exemption from General Design Criterion 57 found in Appendix A to 10 CF Part 50 is described in the Office of Nuclear Reactor Regulation's Safety Evaluat on Report, Supplement No.5, Section 6.2.3.1. This Exemption is authorized by law and will not endanger life or property or the common defense and security and is otherwis in the public interest. The exemption, therefore, is hereby granted and shall remain i effect through the first refueling outage as discussed in Section 6.2.3.1 of Supplem nt 5 to the Safety Evaluation Report. The granting of the exemption is authorize with the issuance of the Facility Operating License, dated May 20, 1981. The facility will perate, to the extent authorized herein, in conformity with the application as amended, he provisions of the Act, and the regulations of the Commission.
G. This renew d license is subject to the following additional condition for the protection of the environ ent:
Before enga ing in additional construction or operational activities which may result in an environme tal impact that was not evaluated by the Commission, PSEG Nuclear LLC shall prepare nd record an environmental evaluation of such activity. When the evaluation indi ates that such activity may result in a significant adverse environmental impact that wa not evaluated, or that is significantly greater than that evaluated in the Final Environm ntal Statement or any addendum thereto, PSEG Nuclear LLC shall provide a writte evaluation of such activities and obtain prior approval from the Director of Nuclear Reac or Regulation.
H. If PSEG Nuclear LC plans to remove or to make significant changes in the normal operation of equi ent that controls the amount of radioactivity in effluents from the Salem Nuclear G eration Station, the NRC shall be notified in writing regardless of whether the chang affects the amount of radioactivity in effluents.
I. DELETED PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP),
including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem-Hope Creek CSP was approved by Renewed License No, DPR-75 License Amendment No. xxx.
Attachment LR-N 11-0208 MARKED-UP TECHNICAL SPECIFICATION PAGES Hope Creek Generating Station Facility Operating License Page 13 4
D. The facility requires exemptions from certain requirements of 10 CFR Part 50 and 10 CFR Part 70. An exemption from the criticality alarm requirements of 10 CFR 70.24 was granted in Special Nuclear Material License No. 1953, dated August 21, 1985. This exemption is described in Section 9.1 of Supplement No.5 to the SER. This previously granted exemption is continued in this operating license. An exemption from certain requirements of Appendix A to 10 CFR Part 50, is described in Supplement No. 5 to the SER. This exemption is a schedular exemption to the requirements of General Design Criterion 64, permitting delaying functionality of the Turbine Building Circulating Water System-Radiation Monitoring System until 5 percent power for local indication, and until 120 days after fuel load for control room indication (Appendix R of SSER 5). Exemptions from certain requirements of Appendix J to 10 CFR Part 50, are described in Supplement No. 5 to the SER. These include an exemption from the requirement of Appendix J, exempting main steam isolation valve leak-rate testing at 1.10 Pa (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing on traversing incore probe system shear valves (Section 6.2.6 of SSER 5); an exemption from Appendix J, exempting Type C testing for instrument lines and lines containing excess flow check valves (Section 6.2.6 of SSER 5); and a~ exemption from Appendix J, exempting Type C testing of thermal relief valves (Section 6.2.6 of SSER 5). These exemptions are authorized by law, will not present an undue risk to the public health and safety, and are consistent with the common defense and security. These exemptions are hereby granted. The special circumstances regarding each exemption are identified in the referenced section of the safety evaluation report and the supplements thereto. These exemptions are granted pursuant to 10 CFR 50.12. With these exemptions, the facility will operate, to the extent authorized herein, in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission.
E. The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, ~raining and qualification, and safeguards contingency plans including amendments made pursuant to provisions of the Miscellaneous Amendmen~s and Search Requirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to the authority of 10 CFR 50.90 and 10 CFR 50.54 (p). The plans, submitted by letter dated May 19, 2006 are entitled: "Salem-Hope Creek Nuclear Generating Station Security Training and Qualification Plan,"
and "Salem-Hope Creek Nuclear Generating Station Security Contingency Plan." The plans contain Safeguards Information protected under 10 CFR 73.21. t Add the following:
PSEG Nuclear LLC shall fully implement and maintain in effect all provisions of the Commission-approved Cyber Security Plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p). The Salem-Hope Creek CSP was approved by License Amendment No. xxx.
Amendment No. +/-+4