NRC Generic Letter 1985-06
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Letter Sequence Request | |
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TAC:63030, (Approved, Closed) | |
Initiation
Administration Questions
Results Other: A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station, ML20126J866, ML20126J973, ML20135E867, ML20149D631, ML20149F003, ML20196E677, ML20196E697, ML20206H162, ML20212B420, ML20214K863, ML20215G661, ML20234C529, ML20234C558, ML20234D524, ML20234D615, ML20234D649, ML20235M565, ML20235Q511, ML20236L543, ML20236N639, ML20236N713, ML20236S088, ML20237B265, ML20237B279 | |
MONTHYEARNRC Generic Letter 1985-061985-04-16016 April 1985
[Table View]NRC Generic Letter 1985-006: Quality Assurance Guidance for ATWS Equipment That Is Not Safety-Related Project stage: Request ML20126J9731985-06-0404 June 1985 Notice of Denial of Amend to License DPR-54 & Opportunity for Hearing Re Proposed Tech Spec Establishing Operability Requirements for Essential HVAC Sys Project stage: Other ML20126J8901985-06-0404 June 1985 Safety Evaluation Supporting Amend 68 to License DPR-54 Project stage: Approval ML20126J8661985-06-0404 June 1985 Amend 68 to License DPR-54,defining Operability & Surveillance Requirements for Plant Essential Electrical Sys & Operability Requirements for Components of Fire Protection Sys Project stage: Other ML20135E8721985-09-0909 September 1985 Safety Evaluation Supporting Amend 74 to License DPR-54 Project stage: Approval ML20135E8671985-09-0909 September 1985 Amend 74 to License DPR-54,revising Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Other ML20135E8571985-09-0909 September 1985 Forwards Amend 74 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Define Testing Requirements for Pressurizer Heaters Powered from Class 1E Power Sources Project stage: Approval ML20215C9951986-10-0202 October 1986 Forwards Replacement Pages Inadvertently Omitted from 860723 Amend 4 to Updated FSAR Re Reactor Vessel & Steam Generator Design Data Project stage: Request ML20212B3781986-12-19019 December 1986 Application for Amend to License DPR-54,consisting of Rev 1 to Proposed Amend 147,changing Electrical Distribution Sys. Design Basis Repts,Response to NRC Question from 861125 Telcon & Summary of Changes Encl Project stage: Request ML20212B4201986-12-19019 December 1986 Proposed Tech Specs Reflecting Changes to Electrical Distribution Sys & Mods to Inverter Power Supply Sys & Undervoltage/Overvoltage Protection Sys.W/Five Oversize Diagrams Project stage: Other ML20234D5241986-12-31031 December 1986 Baseline Vibration Survey Emergency Diesel Generator 'A' Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6151986-12-31031 December 1986 Pipe Vibration Survey Emergency Diesel Generator 'A' Rancho Seco Nuclear Power Plant Project stage: Other ML20234D6491987-01-31031 January 1987 Crankshaft Torsional Vibration Measurements Emergency Diesel Generator 'A' Rancho Seco Nuclear Power Plant Project stage: Other A11745, Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station1987-02-28028 February 1987 Evaluation of DSR-48 Emergency Diesel Generator Crankshafts at Rancho Seco Nuclear Generating Station Project stage: Other ML20206H1281987-04-0101 April 1987 Application for Amend to License DPR-54,revising &/Or Adding Addl Sections to Tech Specs & Addressing Safety Impact of Bringing Tdi Diesel Generators Into Svc. Description of Proposed Changes Encl Project stage: Request IR 05000312/19870081987-04-0101 April 1987 Insp Rept 50-312/87-08 on 870209-0306.No Violations Noted. Major Areas Inspected:Licensee Program for Environ Qualified Electrical splices,follow-up of Insp Open Items,Ie Bulletins & Info Notices,Unresolved Items & LERs Project stage: Request ML20206E0561987-04-0101 April 1987 Commits to Broadening Scope of 870226 Upgrade of Meteorological Sys to Include Installation of fixed-width Guyed Tower Approx 120 Yards Southwest of Existing Tower,Per 870211 Meeting.Schedule Will Be Submitted within 30 Days Project stage: Meeting ML20206H1621987-04-0101 April 1987 Proposed Tech Specs Re Safety Impact of Bringing Tdi Diesel Generators on Line Project stage: Other ML20215G6611987-04-13013 April 1987 Informs That Seismic Qualification of Either of Listed Options Re Resolution of Issue of Class 1 Indication of Tdi Diesel Generator Status in Control Room Will Be Based on Generic Ltr 87-02,per 870401 Commitment Project stage: Other ML20214K8631987-05-18018 May 1987 Informs That Validations Re Tdi Diesel Generator Insps Completed & Phase I Rept Progressing Well.Some Difficulties Prevented Completion of Test Program & Rept to Support 870515 Submittal Date.Interim Rept Expected by 870630 Project stage: Other ML20234C5581987-06-10010 June 1987 Rev 0 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20234C5291987-06-26026 June 1987 Forwards Rev 0 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Per Discussions on 870602 & 03 Re Rev 2 to Proposed Amend 147 to License Project stage: Other ML20235M5651987-07-0808 July 1987 Forwards Design Review/Quality Revalidation (Dr/Qr) Program for Rancho Seco Tdi Diesel Generators, Final Engineering Summary Rept.Preliminary Turbocharger Final Rept Will Be Submitted by 871001 Project stage: Other ML20236N7131987-08-0505 August 1987 Part 21 Rept Re Potential Problem W/Vibration in Lube Oil & Jacket Water Sys.At Rancho Seco Site,Fatigue Cracks Found in Welds of Support Members in Lubricating Oil Sys.Cracks Due to Vibration in Lube Oil Sys.Addl Preventive Action Taken Project stage: Other ML20235F5251987-09-22022 September 1987 Forwards Supplemental Info Re Previous Submittal of Proposed Amend 147,Rev 2 Re Electrical Sys Tech Specs.Info Reflects More Restrictive Limiting Condition of Operation for Diesel Generators to Be out-of-svc Project stage: Supplement ML20235F5301987-09-22022 September 1987 Proposed Tech Specs Consisting of Supplemental Info to Proposed Amend 147,Rev 2 Re Diesel Generator Outages Project stage: Supplement ML20235Q4781987-10-0101 October 1987 Application for Proposed Amend 164 to License DPR-54, Consisting of Enhancements to Tech Specs to Resolve Certain Comments Resulting from NRC Region V Feb & Mar 1987 Contracted Comparison of Plant Tech Specs to Sts.Fee Paid Project stage: Request ML20235Q5111987-10-0101 October 1987 Proposed Tech Specs Re Comparison of Plant Tech Specs to STS Project stage: Other ML20235V7111987-10-0808 October 1987 Informs That Final Design Review/Quality Revalidation Program & Remaining Responses to NRC 840131 Request Will Be Submitted by 871211.Delay in Submitting Response Due to Vibration Problems Project stage: Request NL-87-1295, Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice1987-10-0808 October 1987 Forwards Supplemental Emergency Diesel Generator Info,Per NRC Request.W/One Oversize Drawing Change Notice Project stage: Supplement ML20236E9361987-10-26026 October 1987 Forwards Response to 871008 Request for Clarification & Info Re Emergency Diesel Generator Review Project stage: Request ML20236L5431987-10-30030 October 1987 Forwards Requested Addl Info Re Proposed Amend 147 to License DPR-54 & Plant Electrical Distribution Sys.Single Failure at Switch 52-4B202 Has No Safety Impact Project stage: Other ML20236N3211987-11-0909 November 1987 Forwards Three Pages Inadvertently Omitted from Util 871030 Response to NRC Request for Addl Info Re Proposed Amend 147 to License DPR-54 Project stage: Request ML20236N6391987-11-0909 November 1987 Confirms That 15% Damping Value Used During Design of Cable Tray Supports in Tdi Diesel Generator Bldg,In Response to Request Project stage: Other ML20236Q2381987-11-10010 November 1987 Forwards Safety Evaluation Supporting Plant Electrical Distribution Sys Design (Ref Tdi Diesel Generators).Approval of Design Required Before Performance of Loss of Offsite Power Test Project stage: Approval ML20236Q2461987-11-10010 November 1987 Safety Evaluation Supporting Util & Related Submittals Re Design Mods to Emergency Electrical Distribution Sys (Ref Tdi Diesel Generators) Project stage: Approval ML20236S0821987-11-17017 November 1987 Supplemental Application for Amend to License DPR-54, Consisting of Suppl 2 to Rev 2 to Proposed Amend 147, Concerning Diesel Generators Project stage: Supplement ML20236S0881987-11-17017 November 1987 Proposed Tech Specs,Consisting of Suppl 2 to Rev 2 to Proposed Amend 147,concerning Diesel Generators Project stage: Other ML20237B2791987-12-0101 December 1987 Rev 2 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20237B2651987-12-0808 December 1987 Forwards Rev 2 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Electrical Installation to Reg Guide 1.75, Per Class 1 & 2 Cable Trays & Raceways Described in NUREG-1286,Section 4.7.3.2 a 1 & 2 Project stage: Other ML20234D5061987-12-29029 December 1987 Forwards Listed S&W & Failure Analysis Assoc Repts Re Vibration on Tdi Emergency Diesel Engines,In Response to M Hartzman 871215 Request for Addl Info Project stage: Request ML20149D6311988-01-0404 January 1988 Forwards Engineering Summary Repts for 16 Tdi Phase I Diesel Generator Components,Containing Detailed Info on Design Review/Quality Revalidation Program.Vibration Problems W/Turbocharger Support Bracket Resolved Project stage: Other ML20149F0031988-02-0101 February 1988 Informs of Intent to Submit Formal Rept Re Vibration Surveillance Program for Tdi Diesel Generators.Actions to Be Taken in Future to Monitor Diesels for Vibration Listed Project stage: Other ML20196E6971988-02-0505 February 1988 Rev 3 to Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75 Project stage: Other ML20149L2391988-02-0909 February 1988 Forwards Amend 94 to License DPR-54 & Safety Evaluation. Amend Changes Tech Specs to Reflect Addition of Two Diesel Generators & Associated Mods to Facility Emergency Electrical Distribution Sys Project stage: Approval ML20196E6771988-02-22022 February 1988 Forwards Rev 3 to ERPT-E0220, Rept on Conformance of Nuclear Svc Electrical Bldg & Diesel Generator Bldg Electrical Installation to Reg Guide 1.75, Presenting Clarification for Actual Configuration at Facility Project stage: Other 1987-12-29 |
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Category:NRC Generic Letter
MONTHYEARML23200A1832023-08-0303 August 2023 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:05000000]] OR [[:Zimmer]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] OR [[:Skagit]] OR [[:Marble Hill]] </code>.Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML17067A2782017-04-18018 April 2017 Non-Power Reactor Closeout of Generic Letter 2016-01, Monitoring of Neutron Absorbing Materials in Spent Fuel Pools for the Armed Forces Radiobiology Research Institute, Docket No. 50-170 (CAC No. A11010) ML17067A4042017-04-17017 April 2017 Washington State University GL 2016-01 Closeout Form Letter for Rtrs with No Credited NAM NRC Generic Letter 2007-012007-02-0707 February 2007 NRC Generic Letter 2007-01: Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients NRC Generic Letter 2006-012006-01-20020 January 2006 NRC Generic Letter 2006-01: Steam Generator Tube Integrity and Associated Technical Specifications NRC Generic Letter 1999-021999-08-23023 August 1999 NRC Generic Letter 1999-002: (Errata): Laboratory Testing of Nuclear-Grade Activated Charcoal NRC Generic Letter 1983-111999-06-24024 June 1999 NRC Generic Letter 1983-011, Supplement 1: Licensee Qualification for Performing Safety Analysis ML0823509351999-06-0303 June 1999 Generic Ltr 99-02 to All Holders of OLs for Nuclear Power Reactors,Except Those Who Have Permanenetly Ceased Operations & Certified That Fuel Permanently Removed from Rv Re Laboratory Testing of nuclear-grade Activated Charcoal ML0311101371999-06-0303 June 1999 Withdrawn NRC Administrative Letter 1999-002: Operating Reactor Licensing Action Estimates NRC Generic Letter 1999-011999-05-0303 May 1999 NRC Generic Letter 1999-001: Recent Nuclear Material Safety and Safeguards Decision on Bundling Exempt Quantities NRC Generic Letter 1998-011999-01-14014 January 1999 NRC Generic Letter 1998-001, Supplement 1: Year 2000 Readiness of Computer Systems at Nuclear Power Plants ML0311101601998-08-0303 August 1998 Withdrawn NRC Administrative Letter 1998-005: Availability of Summaries in Electronic Format of Technical Reports by Office for Analysis & Evaluation of Operational Data NRC Generic Letter 1998-041998-07-14014 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 NRC Generic Letter 1998-031998-06-22022 June 1998 NRC Generic Letter 1998-003; NMSS Licensees and Certificate Holders Year 2000 Readiness Programs NRC Generic Letter 1998-021998-05-28028 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 NRC Generic Letter 1997-061997-12-30030 December 1997 NRC Generic Letter 1997-006: Degradation of Steam Generator Internals NRC Generic Letter 1997-051997-12-17017 December 1997 NRC Generic Letter 1997-005: Steam Generator Tube Inspection Techniques NRC Generic Letter 1996-061997-11-13013 November 1997 NRC Generic Letter 1996-006, Supplement 1: Assurance of Equipment Operability and Containment Integrity During Design Basis Accident Conditions ML0312007011997-10-0808 October 1997 Withdrawn NRC Generic Letter 1991-018, Revision 1: Information to Licensees Regarding NRC Inspection Manual Section on Resolution of Degraded and Nonconforming Conditions NRC Generic Letter 1997-041997-09-30030 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 1997-031997-07-0909 July 1997 NRC Generic Letter 1997-003: Annual Financial Surety Update Requirements for Uranium Recovery Licensees NRC Generic Letter 1997-021997-05-15015 May 1997 NRC Generic Letter 1997-002: Revised Contents of Monthly Operating Report NRC Generic Letter 1995-061997-01-31031 January 1997 NRC Generic Letter 1995-006: Changes in Operator Licensing Program NRC Generic Letter 1996-081996-12-15015 December 1996 NRC Generic Letter 1996-008: Interim Guidance on Transportation of Steam Generators NRC Generic Letter 1996-051996-09-18018 September 1996 NRC Generic Letter 1996-005: Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves NRC Generic Letter 1996-041996-06-26026 June 1996 NRC Generic Letter 1996-004: Boraflex Degradation in Spent Fuel Pool Storage Racks NRC Generic Letter 1995-091996-04-0505 April 1996 NRC Generic Letter 1995-009: Supplement 1: Monitoring and Training of Shippers and Carriers of Radioactive Materials NRC Generic Letter 1996-021996-02-13013 February 1996 NRC Generic Letter 1996-002: Reconsideration of Nuclear Power Plant Security Requirements Associated with an Internal Threat NRC Generic Letter 1996-031996-01-31031 January 1996 NRC Generic Letter 1996-003: Relocation of the Pressure Temperature Limit Curves & Low Temperature Overpressure Protection System Limits NRC Generic Letter 1989-101996-01-24024 January 1996 NRC Generic Letter 1989-010, Supplement 7: Consideration of Valve Mispositioning in Pressurized-Water Reactors NRC Generic Letter 1996-011996-01-10010 January 1996 NRC Generic Letter 1996-001: Testing of Safety-Related Logic Circuits NRC Generic Letter 1995-101995-12-15015 December 1995 NRC Generic Letter 1995-010: Relocation of Selected Technical Specifications Requirements Related to Instrumentation ML0310701501995-10-31031 October 1995 Withdrawn - NRC Generic Letter 1995-008: 10 CFR 50.54(p) Process for Changes to Security Plans Without Prior NRC Approval NRC Generic Letter 1993-031995-10-20020 October 1995 NRC Generic Letter 1993-003: Verification of Plant Records NRC Generic Letter 1995-071995-08-17017 August 1995 NRC Generic Letter 1995-007: Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves NRC Generic Letter 1995-041995-04-28028 April 1995 NRC Generic Letter 1995-004: Final Disposition of the Systematic Evaluation Program Lesson-Learned Issues NRC Generic Letter 1995-031995-04-28028 April 1995 NRC Generic Letter 1995-003: Circumferential Cracking of Steam Generator Tubes NRC Generic Letter 1995-021995-04-26026 April 1995 NRC Generic Letter 1995-002: Use of Numarc/Epri Report TR-102348, Guideline on Licensing Digital Upgrades, in Determining the Acceptability of Performing Analog-To-Digital Replacements Under 10CFR 50.59 NRC Generic Letter 1995-011995-01-26026 January 1995 NRC Generic Letter 1995-001: NRC Staff Technical Position on Fire Protection for Fuel Cycle Facilities ML0312004431994-09-0202 September 1994 Withdrawn - NRC Generic Letter 1994-004: Voluntary Reporting of Additional Occupational Radiation Exposure Data NRC Generic Letter 1994-031994-07-25025 July 1994 NRC Generic Letter 1994-003: Intergranular Stress Corrosion Cracking of Core Shrouds in Boiling Water Reactors NRC Generic Letter 1994-021994-07-11011 July 1994 NRC Generic Letter 1994-002: Long-Item Solutions and Upgrade of Interim Operating Recommendations for Thermal Hydraulic Instabilities in Boiling Water Reactors NRC Generic Letter 1994-011994-05-31031 May 1994 NRC Generic Letter 1994-001: Removal of Accelerated Testing and Special Reporting Requirements for Emergency Diesel Generators NRC Generic Letter 1993-081993-12-29029 December 1993 NRC Generic Letter 1993-008: Relocation of Technical Specification Tables of Instrument Response Time Limits NRC Generic Letter 1993-071993-12-28028 December 1993 NRC Generic Letter 1993-007: Modification of Technical Specification Administrative Control Requirements for Emergency & Security Plans NRC Generic Letter 1993-061993-10-25025 October 1993 NRC Generic Letter 1993-006: Research Results on Generic Safety Issue 106, Piping and the Use of Highly Combustible Gases in Vital Areas. NRC Generic Letter 1993-051993-09-27027 September 1993 NRC Generic Letter 1993-005: Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation NRC Generic Letter 1993-041993-06-21021 June 1993 NRC Generic Letter 1993-004: Rod Control System Failure and Withdrawal of Rod Control Cluster Assemblies, 10 CFR 50.54(f) NRC Generic Letter 1993-021993-03-23023 March 1993 NRC Generic Letter 1993-002: Public Workshop on Commercial Grade Procurement and Dedication NRC Generic Letter 1993-011993-03-0303 March 1993 NRC Generic Letter 1993-001: Emergency Response Data System Test Program 2023-08-03 |