Category:Letter type:ULNRC
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Pages in category "Letter type:ULNRC"
The following 200 pages are in this category, out of 890 total.
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- ULNRC-04158, Transmittal of Figure 14.9, Callaway Plant Pressure and Temperature Limits Report (Ptlr), Rev. 3
- ULNRC-04592, Proposed Revision to Technical Specification 1.1, Definitions; Technical Specification 3.7.3 Main Feedwater Isolation Valves (Mfivs); and Steam Generator Tube Rupture with Overfill Re-Analysis
- ULNRC-04595, Special Report 2001-02 for Callaway Plant Unit 1 Re Results of the Twelfth Steam Generator Tube In-Service Inspection
- ULNRC-04617, Response to Request for Additional Information on Revision to Technical Specification 5.5.9 Steam Generator (SG) Tube Surveillance Program.
- ULNRC-04621, Day Response to NRC Order for Interim Safeguards and Security Compensatory Measures
- ULNRC-04622, Request for Extension of Time to Submit an Answer or Request a Hearing
- ULNRC-04625, Annual Financial Report for Callaway Plant
- ULNRC-04626, Union Nuclear Property Insurance Reporting
- ULNRC-04635, Revision to Technical Specification 3.5.5 Seal Injection Flow.
- ULNRC-04638, Response Time Testing Elimination
- ULNRC-04649, Special Report 2002-002 Re Primary Meteorological Tower 10 & 60 Meter Wind Speed Indications Inaccurate Due to Electrical Interference
- ULNRC-04653, Reply to Notice of Violation for Inspection Report 50-483/2002-007, Enforcement Action EA-02-046
- ULNRC-04658, Supplement to 20-Day Response to NRC Security Order for Interim Safeguards and Security Compensatory Measure
- ULNRC-04659, Withdrawal of License Amendment Re Changes to the NRC Approved Fire Protection Program
- ULNRC-04705, Revision to Technical Specification 5.5.9 Steam Generator (SG) Tube Surveillance Program.
- ULNRC-04717, Full Compliance with Order for Interim Safeguards and Security Compensatory Measures
- ULNRC-04721, Technical Specification Bases Revision 3
- ULNRC-04731, Response to NRC Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs.
- ULNRC-04742, Revision to Technical Specification 3.1.8, Physics Tests Exceptions - Mode 2.
- ULNRC-04743, Revision to SG Water Level Low Low LCO Applicability & Allowable Values in TS 3.3.1 & 3.3.2
- ULNRC-04751, 10CFR50.46 Annual Report ECCS Evaluation Model Revisions
- ULNRC-04760, Request for Relief from ASME Section III Requirements Regarding Non-Destructive Examination of Welds Performed Under Site Repair/Replacement Program
- ULNRC-04765, Operating License Appendix B Report Unanticipated Cooling Tower Basin Ph Excursion
- ULNRC-04768, Amerenue - Revision to Request for Relief from ASME Section III Requirements Regarding Non-Destructive Examination of Welds Performed Under Site Repair/Replacement Program for Callaway, Unit 1
- ULNRC-04776, C-3 Classified Inservice Inspection Results for Steam Generator Tube Inspections
- ULNRC-04778, Special Report 2002-04 Inservice Inspection Results for Steam Generator Tube Inspections - Number of Tubes Plugged or Repaired
- ULNRC-04783, Response to Information Requested 30 Days After the Next Refueling Outage by NRC Bulletins 2001-01, 2002,01, & 2002-02
- ULNRC-04786, Request for Enforcement Discretion to Allow Additional Time for Restoration of Inoperable Turbine Driven Auxiliary Feedwater Pump (NOED 02-4-004)
- ULNRC-04787, Core Operating Limits Report
- ULNRC-04794, Core Operating Limits Report, Revisions 1 and 2
- ULNRC-04798, Twenty-Day Answer to NRC Order for Compensatory Measures Related to Access Authorization
- ULNRC-04799, Response to Request for Additional Information - NRC Bulletin 2002-01, Reactor Pressure Vessel Head Degradation & Reactor Coolant Pressure Boundary Integrity.
- ULNRC-04807, Revision to Request for Relief from ASME Section III Requirements Regarding Non-Destructive Examination of Welds Performed Under Site Repair/Replacement Program
- ULNRC-04813, Ameren/Ue, Response to Order EA-03-009, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.
- ULNRC-04819, Results of Chemical Analysis of Reactor Vessel Head Debris Found During Bare Metal Examination in Refuel 1
- ULNRC-04822, Response to Request for Information EA-03-040, Callaway Plant, Union Electric Co
- ULNRC-04823, Results of Thirteenth Steam Generator Tube In-Service Inspection
- ULNRC-04826, Union Electric Annual Financial Report
- ULNRC-04827, Property Insurance Reporting
- ULNRC-04828, Service List Update
- ULNRC-04829, Nuclear Decommissioning Planning, 10 CFR 50.75(f)(1)
- ULNRC-04837, License Amendment Request OL-1228 Revision to Technical Specification Surveillance Requirements 3.8.1 and 3.8.4
- ULNRC-04838, 2002 Annual Environmental Operating Report for Callaway Plant
- ULNRC-04840, Annual Radioactive Effluent Release Report
- ULNRC-04844, Operating Quality Assurance Manual, Revision 23
- ULNRC-04848, Reply to Preliminary White Finding Regarding Inspection Report No. 50-483/2003-008
- ULNRC-04851, CFR 50.59 Summary Report, July 2001 - December 2002
- ULNRC-04853, Physical Security Plan, Revision 36
- ULNRC-04854, Revision to TS 3.8.3, Diesel Fuel Oil, Lube Oil, & Starting Air
- ULNRC-04856, Technical Specification Bases, Revision 4
- ULNRC-04857, Union Electric Co., Callaway Plant Unit 1, Supplemental Response to the April 29, 2003, Orders to Callaway
- ULNRC-04858, Answer, Response and Request for Clarification in Response to April 29, 2003, Order for Compensatory Measures Related to Training Enhancements on Tactical and Firearms Proficiency and Physical Fitness Applicable to Armed Nuclear Power Pl
- ULNRC-04859, Callaway, Answer, Response and Request for Clarification in Response to April 29, 2003, Order for Compensatory Measures Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel (EA-03-038)
- ULNRC-04861, Revision to Technical Specification 5.5.9 Steam Generator Tube Surveillance Program
- ULNRC-04866, License Amendment Request OL-1225 Revision to TSs for Extension of Required Action Completion Time for Diesel Generators
- ULNRC-04867, Reply to Notice of Violation Inspection Report No. 50-483/2003-008
- ULNRC-04868, Application of Proprietary Leak-Before-Break (LBB) Methodology Reports and Draft Regulatory Guide DG-1108
- ULNRC-04869, Core Operating Limits Report
- ULNRC-04870, Service List Update
- ULNRC-04875, Request for Relief from ASME Section XI Requirements in Order to Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement
- ULNRC-04878, Supplemental Answer to April 29, 2003 Order for Compensatory Measures Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel
- ULNRC-04879, Requests for Relief Regarding Implementation of ASME Section XI Appendix VII Requirements
- ULNRC-04884, Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
- ULNRC-04885, Response to Request for Information on Generic Letter 2003-01, Control Room Habitability.
- ULNRC-04892, Request for Additional Information on November 2002 Steam Generator Tube Inspection
- ULNRC-04894, Physical Security Plan, Revision 37
- ULNRC-04898, Request for NRC Regional Enforcement Discretion
- ULNRC-04901, Response to NRC Regulatory Issue Summary 2003-14, Preparation and Scheduling of Operator Licensing Examinations.
- ULNRC-04907, NPDES Permit Renewal
- ULNRC-04908, Decommissioning Funding Report, Supplemental Information
- ULNRC-04909, Response to RAI Regarding License Amendment Request OL-1228 (Revision to Technical Specification Surveillance Requirements 3.8.1 and 3.8.4)
- ULNRC-04910, Full Compliance with Order for Compensatory Measures Related to Fitness-for-Duty Enhancements Applicable to Nuclear Facility Security Force Personnel, Dated April 29, 2003
- ULNRC-04911, Response to Request for Additional Information Regarding License Amendment Request OL-1225 (Revision to Technical Specifications for Extension of Required Action Completion Time for Diesel Generators)
- ULNRC-04912, 10 CFR 21 Notification for GE Magne-Blast Breaker Tube and Piston Assemblies
- ULNRC-04918, Request for Enforcement Discretion
- ULNRC-04920, Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity
- ULNRC-04926, Application of Proprietary Leak-Before-Break (LBB) Methodology Reports and Draft Regulatory Guide DG-1108
- ULNRC-04928, Responses to RAIs on the Proposed Revision to Technical Specification (TS) 1.1, Definitions, TS 3.7.3, Main Feedwater Isolation Valves (Mfivs), and Steam Generator Tube Rupture with Overfill Re-Analysis
- ULNRC-04931, Response to NRC Bulletin 2003-04, Rebaselining of Data in the Nuclear Materials Management and Safeguards System.
- ULNRC-04932, NPDES Permit Proposed Change Concerning the Schedule of Compliance for Groundwater Monitoring
- ULNRC-04933, Full Compliance with Order for Compensatory Measures Related to Access Authorization, Dated 01/07/2003
- ULNRC-04937, Transmittal of an Updated Addressee List for Correspondence
- ULNRC-04939, Response to 11/12/03 Meeting Questions Regarding Application of Proprietary Leak-Before-Break (LBB) Methodology Reports and Draft Regulatory Guide DG-1108
- ULNRC-04942, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement
- ULNRC-04943, Quality Assurance Program for Packaging and Transportation of Radioactive Materials
- ULNRC-04945, Callaway Plan, DEFENSE-IN-DEPTH and Diversity Assessment for Digital Upgrade of Callaway'S Instrumentation and Control Systems (License Amendment Request OL-1249)
- ULNRC-04950, Transmittal of an Updated Addressee List for Correspondence Generated by the NRC
- ULNRC-04957, Response to Order EA-03-009, Revision 1, Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors.
- ULNRC-04960, Transmittal of NPDES Permit Renewal
- ULNRC-04962, Nuclear Property Insurance Reporting
- ULNRC-04963, Annual Financial Report for 2002
- ULNRC-04966, Union Electric Co., Supplement to Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
- ULNRC-04968, 10CFR 50.46 Annual Report, ECCS Evaluation Model Revisions
- ULNRC-04969, Supporting Information and Follow-Up Request Regarding License Amendment Request OL-1228 for Revision to Technical Specifications 3.8.1, AC Sources - Operating, and 3.8.4, DC Sources - Operating.
- ULNRC-04971, Guarantee of Payment of Retrospective Premiums 10 CFR 140.21
- ULNRC-04974, Application of Proprietary Leak-Before-Break (LBB) Methodology Reports and Draft Regulatory Guide DG-1108
- ULNRC-04975, Application for Technical Specification Improvement to Extend the Inspection Interval for Reactor Coolant Pump Flywheels Using the Consolidated Line Item Improvement Process
- ULNRC-04977, License Amendment Application Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process
- ULNRC-04990, Annual Environmental Operating Report
- ULNRC-04991, 2003 Annual Radioactive Effluent Release Report
- ULNRC-04993, Revision of Request for Relief from ASME Section XI Requirements in Order to Temporarily Restore Wall Thickness of ASME Class 2 Carbon Steel Main Feedwater Piping by Weld Overlay Reinforcement
- ULNRC-04997, Revision to Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program
- ULNRC-05007, Core Operating Limits Report
- ULNRC-05021, Application of Proprietary Leak-Before-Break Methodology, Reports and Draft Regulatory Guide DG-1108
- ULNRC-05024, Request for Relief for Plant Inservice Inspection Program
- ULNRC-05026, Response to Request for Additional Information Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-water Reactors
- ULNRC-05031, Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.
- ULNRC-05042, Response to Information Requested 60 Days After the Next Refueling Outage by NRC Bulletin 2003-02 and First Revised NRC Order EA-03-009
- ULNRC-05049, Union Electric Company Callaway Plant Request for Relief from ASME Section XI Code Inservice Examination Requirements
- ULNRC-05056, Technical Specification Revisions Associated with Steam Generator Replacement Project
- ULNRC-05060, Response to Request for Additional Information on Amendment Application on Mode Change Relaxations
- ULNRC-05061, Withdrawal of Initial Defense-in-Depth and Diversity Assessment for Digital Upgrade of Callaway'S Instrumentation and Control Systems
- ULNRC-05063, Commitment Tracking System Summary of Commitment Revisions and Deletions Fuel Cycle Thirteen
- ULNRC-05064, Request for Relief Inservice Inspection Program, Ref. ULNRC-05024, 07/06/2004
- ULNRC-05070, Deletion of Operating License Section 2.F, Deletion or Revision of License Conditions and Revision to Technical Specification Tables 5.5.9-2 and 5.5.9.3
- ULNRC-05072, Response to NRC Generic Letter 2004-01: Requirements for Steam Generator Tube Inspections
- ULNRC-05073, Response to Request for Additional Information on Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Testing Times, Completion Times and Surveillance Test Intervals
- ULNRC-05074, Application for Technical Specification Improvement to Eliminate Requirements to Provide Monthly Operating Reports and Occupational Radiation Exposure Reports Using the Consolidated Line Item Improvement Process
- ULNRC-05082, Service List Update
- ULNRC-05087, Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals
- ULNRC-05089, Special Report on the Inoperability of Unit Vent High Range Radiation Monitor
- ULNRC-05090, Extension of Current 10-Year Inservice Testing Interval
- ULNRC-05092, Revision to Approve Request for Relief from ASME Section III Requirements Regarding Non-destructive Examination of Welds Performed Under Site Repair/Replacement Program
- ULNRC-05097, Transmittal of Proprietary Information for the Next Revision of the Significance Determination Process Risk-informed Inspection Notebook
- ULNRC-05098, CFR 50.59 Summary Report from January 1, 2003 Through June 30, 2004
- ULNRC-05100, Transmittal of Inservice Inspection, Summary Report for Refuel 13 and WCAP-16280-P, Flaw Evaluation Handbook for Plant Reactor Vessel Inlet Nozzle Safe-End Weld Region, May 2004
- ULNRC-05101, Union Electric Co. Technical Specification Bases Revision 5
- ULNRC-05104, Response to Generic Letter 2003-01, Control Room Habitability.
- ULNRC-05107, Service List Update
- ULNRC-05117, Technical Specification Revisions Associated with the Steam Generator Replacement Project
- ULNRC-05118, Response to Request for Additional Information Regarding Requests for Relief from ASME Section XI Code Inservice Examination Requirements (ISI-24, ISI-25 and ISI-26)
- ULNRC-05123, Transmittal of 10CFR50.46 Thirty-Day Report Regarding ECCS Evaluation Model Revision
- ULNRC-05124, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
- ULNRC-05129, Union Electric Company Amended 10 CFR 50.46 Thirty Day Report ECCS Evaluation Model Revisions
- ULNRC-05130, Nuclear Decommissioning Planning 10 CFR 50.75(F)(1)
- ULNRC-05135, Nuclear Property Insurance Reporting
- ULNRC-05136, Union Electric Company Annual Financial Report
- ULNRC-05138, Application for Amendment, Proposed Amendment Would Add New Technical Specification (TS) LCO 3.1.9, RCS Boron Limitations ≪ 500F, and Revise TS 3.3.1, Reactor Trip System (RTS) Instrumentation.
- ULNRC-05140, Annual Radioactive Effluent Release Report
- ULNRC-05141, Annual Environmental Operating Report
- ULNRC-05143, Request to Apply Subsequent ASME Section XI Code Edition and Addenda for Site Repair/Replacement Program
- ULNRC-05145, Technical Specification Revisions Associated with the Steam Generator Replacement Project
- ULNRC-05147, Response to April 11, 2005, NRC Letter Regarding Implementation of November 5, 2004, Order Imposing Requirements for Protection of Safeguards Information (EA-04-190)
- ULNRC-05152, Request for Authorization for Use of Delta Protection Respiratory Protection Equipment
- ULNRC-05162, License Amendment Request OL-1217 for Callaway Plant Union Electric Company Response to Request for Additional Information Deletion of Operating License Section
- ULNRC-05163, Annual Radiological Environmental Operating Report
- ULNRC-05165, Withdrawal of License Amendment Request OL-1225 Regarding Proposed Changes to Technical Specifications for Extension of Required Action Completion Times for Diesel Generators
- ULNRC-05169, Technical Specification Revisions Associated with the Steam Generator Replacement Project
- ULNRC-05170, Response to Request for Additional Information Authorization for Use of Delta Protection Respiratory Protection Equipment
- ULNRC-05174, Union Electric Co., Revision to Technical Specification 3.6.6, Containment Spray and Cooling Systems
- ULNRC-05178, Technical Specification Revisions Associated with the Steam Generator Replacement Project
- ULNRC-05183, Requests for Relief from ASME Section XI Code Inservice Examination Requirements
- ULNRC-05184, 10CFR50.55a(a)(3) Requests for Relief from ASME OM Code Pump Testing Requirements for Third 120-Month Inservice Testing Interval
- ULNRC-05185, Request for Relief from ASME Section XI Code Inservice Examination Requirements
- ULNRC-05187, Inoperable Channel 3 of the Loose Parts Detection System (Lpds)
- ULNRC-05188, Technical Specification Revisions Associated with the Steam Generator Replacement Project
- ULNRC-05192, Supplemental Technical Specification Revisions for the Steam Generator Replacement Project
- ULNRC-05194, Response to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.
- ULNRC-05197, Request for Approval of Changes to Reactor Coolant System Leakage Detection Methodology
- ULNRC-05205, Callaway'S Supplemental Response to NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors
- ULNRC-05206, License Amendment Request OL 1258 Revision to Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfiv'S)
- ULNRC-05216, Response to Request for Additional Information Related to Section B.5.B of the Interim Safeguards and Security Compensatory Measures
- ULNRC-05219, Pressure and Temperature Limits Report, Revision 4, Incorporating Changes Associated with the Replacement Steam Generator Program
- ULNRC-05224, Supplement/Revision to License Amendment Request OL-1258 for Revision of Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfivs).
- ULNRC-05226, Responses to Requests for Additional Information Concerning License Amendment Request (LAR) OL-1258 for Revision of Technical Specification 3.7.3, Main Feedwater Isolation Valves (Mfivs).
- ULNRC-05228, Core Operating Limits Report, Rev. 0
- ULNRC-05232, Letter of Intent to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants, 2001 Edition
- ULNRC-05233, Application for Amendment to Facility Operating License NPF-30
- ULNRC-05234, Withdrawal of Request for Authorization for Use of Delta Products Mururoa Blu Self Feed Single Use Suits
- ULNRC-05235, Commitment Statue for NRC Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors.
- ULNRC-05236, Withdrawal of 10 CFR 50.55(a)(3) Request for Relief from ASME OM Code Pump Testing Requirements for Residual Heat Removal Pumps
- ULNRC-05237, Special Report - Inoperable Channel 5 of the Loose Parts Detection System (Lpds)
- ULNRC-05239, Request for Extension of Time within Which to Respond to Demand for Information
- ULNRC-05242, Response to Request for Additional Information on Reactor Coolant System Leakage Detection Instrumentation
- ULNRC-05248, Submittal of Revision 23 to Pump and Valve Inservice Testing Program
- ULNRC-05250, Commitment Tracking System Summary of Commitment Revisions and Deletions Fuel Cycle Fourteen
- ULNRC-05253, Additional Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized-Water Reactors.
- ULNRC-05259, Response to Request for Additional Information Re License Amendment Request (LAR) OL-1262 for Revision of Technical Specification 3.7.2, Main Steam Isolation Valves (Msivs).
- ULNRC-05260, ECCS Evaluation Model Revisions
- ULNRC-05265, Nuclear Property Insurance Reporting
- ULNRC-05267, Proposed Revision to Technical Specification 5.0 Administrative Controls (License Amendment Request OL 1267)
- ULNRC-05268, Annual Financial Report
- ULNRC-05269, Proposed Revision to Technical Specification 3.9.2 Unborated Water Source Isolation Valves and Associated Revisions to Technical Specification 3.3.9 Boron Dilution Mitigation System (Bdms) (License Amendment Request OL 1238)
- ULNRC-05270, 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and Operability of Offsite Power.
- ULNRC-05271, 10 CFR 50.55a Requests for Relief from ASME Section XI Inservice Inspection Requirements for Third 10-Year Inspection Interval
- ULNRC-05277, Annual Radioactive Effluent Release Report
- ULNRC-05278, Annual Report of Individual Monitoring Results
- ULNRC-05280, Proposed Revision to Technical Specification 3.7.2 Main Steam Isolation Valves and Revision to Technical Specification 3.7.3 Main Feedwater Isolation Valves and Main Feedwater Regulating Valve Bypass Valves to Remove Valve Isolation Time
- ULNRC-05281, Application for Amendment to Facility Operating License NPF-30, Adoption of Industry Traveler TSTF-490
- ULNRC-05287, CFR 50.59 Summary Report
- ULNRC-05291, CFR 50.55a Requests for Relief from ASME Section XI Inservice Inspection Requirements for Third 10-Year Inspection Interval (Relief Requests 13R-05 and 13R-06)
- ULNRC-05292, Clarification of Response to Request for Additional Information Regarding 10 CFR 50.55a Request to Support Application of Structural Weld Overlays for Pressurizer Nozzle Welds
- ULNRC-05293, Revision to Technical Specification 3.5.2, ECCS - Operating, and 3.6.7, Recirculation Fluid Ph Control System.
- ULNRC-05294, Day Response to NRC Generic Letter 2006-03, Potentially Nonconformance Hemyc and MT Fire Barrier Configurations.
- ULNRC-05295, Response Update to Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
- ULNRC-05297, Proposed Revision to Technical Specifications for Use of Beacon Power Distribution Monitoring System
- ULNRC-05298, Amended Response to Generic Letter 2003-01, Control Room Habitability.
- ULNRC-05301, Proposed Revision to Technical Specification TSs 3.7.10, 3.7.11 and 3.7.13
- ULNRC-05307, Revision to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation
- ULNRC-05309, Inoperable Channel 11 of the Loose Parts Detection System (Lpds)