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Issue date | Title | |
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LR-N22-0041, 2021 Annual Radioactive Effluent Release Report (Rerr) | 28 April 2022 | 2021 Annual Radioactive Effluent Release Report (Rerr) |
IR 05000272/2017003 | 27 June 2018 | Integrated Inspection Report 05000272/2017003 and 05000311/2017003 |
ML18134A337 | 14 May 2018 | NRC Response to PSEG Contested NCV in Inspection Report 05000272/2017003 and Associated Backfit Claims - EA-17-198 |
ML18135A284 | 7 May 2018 | CRGR Response to Region I Regarding the Contested NCV on the Salem Containment Isolation Valves and Associated Backfit Claims |
ML17335A118 | 25 January 2018 | Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai Ichi Accident |
ML18009A953 | 9 January 2018 | U.S. Nuclear Regulatory Commission Response to Disputed Notice of Non-Cited Violation 05000272/2017003-02 |
LR-N17-0188, Response to Integrated Inspection Report 05000272/2017003 and 05000311/2017003 | 14 December 2017 | Response to Integrated Inspection Report 05000272/2017003 and 05000311/2017003 |
ML15174A257 | 1 September 2015 | Letter to Licensees Coordination of Request for Information for Flooding Hazard Reevaluations and Mitigating Strategies for Beyond-Design-Basis External Events |
ML14111A147 | 9 May 2014 | Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights |
ML14030A046 | 20 February 2014 | Letter from Eric J. Leeds Supplemental Information Related to Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 |
ML12054A735 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12054A679 | 12 March 2012 | Issuance of Order to Modify Licenses with Regard to Reliable Spent Fuel Pool Instrumentation |
ML12056A045 | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
ML12056A044 | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
NRC-2012-0067, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status | 12 March 2012 | Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Effective Immediately) - to All Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status |
NRC-2012-0068, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events | 12 March 2012 | Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events |
CY-92-223, G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 | 14 July 2011 | G20110523/LTR-11-0411/EDATS: SECY-2011-0411 - Ltr. from Rep. E.J. Markey to Chairman Jaczko NRC Safety Requirements for Reactors Granted Construction Permits Prior to 1971 |
ML101440280 | 29 April 2010 | Salem, Units 1 & 2 and Hope Creek, Unit 1 - Response to NRC Request for Additional Information Dated 04/16/2010 Related to the Environmental Review, License Renewal Application, Ecology, Question # ECO-7 |
NRC Generic Letter 2006-01 | 20 January 2006 | NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications |
ML031110449 | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
RIS 1999-02, Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes | 13 October 1999 | Relaxation of Technical Specification Requirements for PORC Review of Fire Protection Program Changes |
NRC Generic Letter 1983-11 | 24 June 1999 | NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis |
ML18107A319 | 21 May 1999 | Review of Submittal in Response to NRC GL-88-20,Suppl 4: 'Ipeees,' Fire Submittal Screening Review Technical Evaluation Rept:Salem Generating Station,Rev 1. |
NRC Generic Letter 1998-01 | 14 January 1999 | NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants |
ML18106A960 | 12 November 1998 | Submits 120-day Response to GL 98-04 Re Impact of Potential Coating Debris on Operation of Safety Related SSC During Postulated Design Basis LOCA |
NRC Generic Letter 1998-04 | 14 July 1998 | NRC Generic Letter 1998-004: Potential for Degradation of the Emergency Core Cooling System and the Containment Spray System After a Loss-of-coolant Accident Because of Construction and Protective Coating Deficiencies and Foreign Material i |
LR-N980284, Comment on PR-50 Re IEEE Std 603-1991 for Salem & Hope Creek Generating Stations.Lack of Adverse Comments to Draft RG Should Not Have Been Construed as Endorsement to IEEE 603-1991 | 12 June 1998 | Comment on PR-50 Re IEEE Std 603-1991 for Salem & Hope Creek Generating Stations.Lack of Adverse Comments to Draft RG Should Not Have Been Construed as Endorsement to IEEE 603-1991 |
NRC Generic Letter 1998-02 | 28 May 1998 | NRC Generic Letter 1998-002: Loss of Reactor Coolant Inventory and Associated Potential for Loss of Emergency Mitigation Functions While in a Shutdown Condition |
ML18106A271 | 31 December 1997 | Monthly Operating Rept for Dec 1997 for Salem Generating Station,Unit 1.W/980115 Ltr |
NRC Generic Letter 1997-06 | 30 December 1997 | NRC Generic Letter 1997-006: Degradation of Steam Generator Internals |
NRC Generic Letter 1997-05 | 17 December 1997 | NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques |
ML18102B656 | 6 November 1997 | Responds to NRC 971008 Ltr Re Violations Noted in Insp Repts 50-272/97-09,50-311/97-09 & 50-311/97-11.C/As:revised Unit 2 RWST Drain Down Evaluation,Revised EOP-LOCA-3 to Support Drain Down re-evaluation & Trained Crews on New Procedure |
NRC Generic Letter 1997-04 | 30 September 1997 | NRC Generic Letter 1997-004: NRC Staff Approval for Changes to 10 CFR Part 50, Appendix H, Reactor Vessel Surveillance Specimen Withdrawal Schedules |
NRC Generic Letter 1997-02 | 15 May 1997 | NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report |
ML18102A946 | 27 March 1997 | Provides Suppl Info to Response to GL 96-06 Re Containment Fan Coil Units |
Information Notice 1997-04, Implementation of a New Constraint on Radioactive Air Effluents | 24 February 1997 | Implementation of a New Constraint on Radioactive Air Effluents |
NRC Generic Letter 1995-06 | 31 January 1997 | NRC Generic Letter 1995-006: Changes in Operator Licensing Program |
ML18102A564 | 15 November 1996 | Provides Results of Reviews of Spent Fuel Storage Pool & Cooling Sys During Current Refueling Outages |
NRC Generic Letter 1996-05 | 18 September 1996 | NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves |
NRC Generic Letter 1996-04 | 26 June 1996 | NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks |
NRC Generic Letter 1996-03 | 31 January 1996 | NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits |
NRC Generic Letter 1989-10 | 24 January 1996 | NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors |
NRC Generic Letter 1996-01 | 10 January 1996 | NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits |
NRC Generic Letter 1995-10 | 15 December 1995 | NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation |
ML18101B193 | 30 November 1995 | Final TER Salem Nuclear Power Station. |
ML18101A942 | 28 August 1995 | Requests Relief from ASME Section III Requirements Manual Isolation Valves in Series W/Relief Devices |
NRC Generic Letter 1995-07 | 17 August 1995 | NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves |
NRC Generic Letter 1995-04 | 28 April 1995 | NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues |
ML18101A632 | 31 March 1995 | Monthly Operating Rept for Mar 1995 for Salem 1.W/950413 Ltr |
ML20080G832 | 6 February 1995 | Comment Opposing Proposed Rule 10CFR50 Re Shutdown & low-power Operations for Npp.Encourages NRC to Reevaluate Regulatory Analyses in Light of Higher Costs.Concludes That Addl Rules on Shutdown & Low Power Operations Not Necessary |