Search by property

This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• ML20056A884  + (Responds to NRC Forwarding Insp Repts 50-206/90-10,50-361/90-10 & 50-362/90-10.Results of Review of Awareness & Response to Industry Check Valve Concerns & Evaluation of Need to Establish Dedicated Program Provided)
• ML20005G119  + (Responds to NRC Forwarding Insp Repts 50-206/89-28,50-361/89-28 & 50-362/89-28 Re Respiratory Protection.Health Physics & Environ Section Will Conform W/ & Utilize Nuclear Oversight Div Procedures)
• ML19323C554  + (Responds to NRC Forwarding NUREG-0662 & Two Addenda.Krypton Gas Should Be Removed as Soon as Possible. Volunteers Svcs to Help Educate & Inform Public)
• ML19350C669  + (Responds to NRC Forwarding NUREG-0737 Re post-TMI Requirements,Action Items II.K.3.16,II.K.3.18 & II.K.3.29. Addl Time Needed to Review Results of Feasibility Studies for Item II.K.3.16.No Action Planned on Item II.K.3.29)
• A01216, Responds to NRC Forwarding NUREG-0737.Util Has Consulted W/B&W on Revisions to Small Break LOCA Model.B&W Will Advise NRC Re Scope & Schedule of Revisions.Util Is Developing in-house Capability to Perform LOCA Analyses  + (Responds to NRC Forwarding NUREG-0737.Util Has Consulted W/B&W on Revisions to Small Break LOCA Model.B&W Will Advise NRC Re Scope & Schedule of Revisions.Util Is Developing in-house Capability to Perform LOCA Analyses)
• ML17328A979  + (Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalties in Amount of $150,000 Per Special Team Insp Repts 50-315/90-18 & 50-316/90-18 Re Design Control Per App R to 10CFR50)
• ML20006E220  + (Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000. Corrective Actions:All Matl Removed from Decon Flush Facility & Entire Facility Decontaminated)
• ELV-03377, Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000. Corrective Actions:Procedures Revised to Add Precaution Re TS Requirements for Reactor Water Makeup Storage Tank  + (Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $100,000. Corrective Actions:Procedures Revised to Add Precaution Re TS Requirements for Reactor Water Makeup Storage Tank)
• ML19324C435  + (Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $280,000 Re Insp Rept 50-344/89-19 & Forwards Payment of Civil Penalty.Corrective Action:Implementation of Plan Underway)
• ML20033E125  + (Responds to NRC Forwarding Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000. Corrective Actions:Review of Historical Svc Water Sys Plant Mods Completed & Unit 2 cross-tie Valves Replaced.Fee Encl)
• A10242, Responds to NRC Forwarding Notice of Violation from Safety Insp Rept 50-423/91-26 on 911127-1220. Corrective Actions:Original Fusible Link Replaced W/Link Rated for 285 F  + (Responds to NRC Forwarding Notice of Violation from Safety Insp Rept 50-423/91-26 on 911127-1220. Corrective Actions:Original Fusible Link Replaced W/Link Rated for 285 F)
• ML19317G450  + (Responds to NRC Forwarding Notice to Employees. Copies of Notice Will Be Posted in Sufficient Number of Places Before 770425)
• ML19210A364  + (Responds to NRC Forwarding Questions Re Plant Operation & Equipment Failures During Degraded Grid Voltage)
• ML19319D460  + (Responds to NRC Forwarding Requests for Addl Info & Regulatory Positions.Full Response Due 731001 in Amend 32 to OL Application)
• ML20087J153  + (Responds to NRC Forwarding Revised Emergency Plan SER & Request for Clarification of Listed Items & Deviation from Commitment.Corrective Actions:Procedure EP 5.0, Organizational Control of Emergencies, Revised)
• ML20126D193  + (Responds to NRC Forwarding Revision 8 to Certificate of Compliance 6400.In Response to Question 2, Lynchburg Research Ctr Has Used Overpacks L-1 & Units 1 & 2. Questions 1 & 3 Do Not Apply)
• B14454, Responds to NRC Forwarding SALP Rept 50-219/91-99 Covering Assessment Period Ending 930109.Training Program Will Be Controlled Via Update to Site Emergency Plan Document & Training Program Re Fire Watches Improved  + (Responds to NRC Forwarding SALP Rept 50-219/91-99 Covering Assessment Period Ending 930109.Training Program Will Be Controlled Via Update to Site Emergency Plan Document & Training Program Re Fire Watches Improved)
• ML20077M480  + (Responds to NRC Forwarding SALP for Feb 1982 - Jan 1983.Realignment of Organizational Responsibilities Initiated.All site-related Activities Consolidated Under Singel Authority)
• ML13329A235  + (Responds to NRC Forwarding Salp.Concludes That commercial-grade Dedication Program Sound,In Compliance W/ GL 89-02 & in Process of Being Upgraded to Be in Full Compliance W/Gl 91-05)
• ML19319C105  + (Responds to NRC Forwarding, ATWS for Water-Cooled Power Reactors. Agrees Facility Is Category B Plant.Full Response to Follow Review of B&W Rept)
• ML19256A924  + (Responds to NRC Forwards Cost Estimates for ATWS Fixes for Units 1 & 4)
• NG-93-3201, Responds to NRC GL 88-14,requesting Licensee Review NUREG-1275,Vol 2, Operating Experience Feedback..., & Perform Design & Operations Verification.Util Reviewed Status of Smaller Components & Assigned Plant Numbers  + (Responds to NRC GL 88-14,requesting Licensee Review NUREG-1275,Vol 2, Operating Experience Feedback..., & Perform Design & Operations Verification.Util Reviewed Status of Smaller Components & Assigned Plant Numbers)
• ML20118A828  + (Responds to NRC GL 88-20,Suppl 4, IPEEE for Severe Accident Vulnerabilities. Milestones & Submittal Schedule Encl)
• ML18011A502  + (Responds to NRC GL 89-10,completion of Motor Operated Valve Test Program Implementation)
• NG-94-3120, Responds to NRC GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs  + (Responds to NRC GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs)

• GO2-96-081, Responds to NRC GL 96-01, Testing of Safety-Related Logic Circuits  + (Responds to NRC GL 96-01, Testing of Safety-Related Logic Circuits)

• RC-96-0258, Responds to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks  + (Responds to NRC GL 96-04, Boraflex Degradation in Spent Fuel Pool Storage Racks)
• ML20137G895  + (Responds to NRC GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions)
• ML20136B359  + (Responds to NRC GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions)
• HNP-96-186, Responds to NRC GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant  + (Responds to NRC GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant)
• NG-97-2237, Responds to NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps  + (Responds to NRC GL 97-04, Assurance of Sufficient Net Positive Suction Head for ECC & Containment Heat Removal Pumps)
• HNP-98-031, Responds to NRC GL 97-05, Steam Generator Tube Insp Techniques, for Harris Nuclear Plant  + (Responds to NRC GL 97-05, Steam Generator Tube Insp Techniques, for Harris Nuclear Plant)
• ML20057B589  + (Responds to NRC GL-89-10,Suppl 5,identifying Test Equipment Which Has Been Utilized at Plant to Date & Summarizing Actions Taken to Address Inaccuracy Issues Associated W/Use of Equipment)
• ML20217J817  + (Responds to NRC GL-98-03,completing Portion Which Applies to Safety & Process Control Activities of Y2K Readiness Program to Assure That Computer Sys Will Not Prevent or Degrade Safety Function of Structure,Sys or Component)
• ML20030B244  + (Responds to NRC Generic Ltr 81-01 Re Qualification of Insp, Exam & Testing & Audit Personnel.Requirements for Reg Guide 1.58 Will Be Implemented.Lead Auditors Will Be Qualified Per Reg Guide 1.146.Commitments Will Be Implemented by 820101)
• ML20009G054  + (Responds to NRC Generic Ltr 81-01 Re Qualification of Insp, Exam & Testing & Audit Personnel.Commits to Compliance W/Reg Guide 1.58,Revision 1 & Reg Guide 1.146 by 811231)
• ML20009F873  + (Responds to NRC Generic Ltr 81-01 Re Qualification of Insp, Exam & Testing & Audit Personnel.Commits to Meet Regulatory Positions C.5,6,7,8 & 10 of Reg Guide 1.58,Revision 1 & Reg Guide 1.146)
• ML20009E991  + (Responds to NRC Generic Ltr 81-01 Requesting Commitments to Regulatory Positions C.5-8 & 10 of Reg Guide 1.58,Revision 1 & Reg Guide 1.46 & Planned Date for Meeting Commitments. FSAR Revision 3 Described Commitments)
• RBG-10-698, Responds to NRC Generic Ltr 81-03 Re NUREG-0313,Revision 1, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping. Review of Stainless Steel Piping Will Be Submitted by 810803  + (Responds to NRC Generic Ltr 81-03 Re NUREG-0313,Revision 1, Technical Rept on Matl Selection & Processing Guidelines for BWR Coolant Pressure Boundary Piping. Review of Stainless Steel Piping Will Be Submitted by 810803)
• ML19352B003  + (Responds to NRC Generic Ltr 81-04 Re Emergency Procedures & Training for Station Blackout Events.Util Evaluation Efforts & Guidelines Re Station Blackout & Plant Procedure Revisions Will Be Completed by Sept & Nov 1981,respectively)
• ML19347E590  + (Responds to NRC Generic Ltr 81-04 Re Emergency Procedures Training for Station Blackout Events.Procedures for Responding to Emergency Situations Are Not Scheduled for Completion Until 6 Months Prior to Initial Fuel Load)
• ML20003F477  + (Responds to NRC Generic Ltr 81-10 Re post-TMI Requirements for Emergency Operations facility.NUREG-0696 Criteria Will Probably Eliminate Facility Planned for Emergency Operations Use.Conceptual Design Date of 810601 May Not Be Met)
• ML19345H237  + (Responds to NRC Generic Ltr 81-10 Requesting Confirmation That Implementation Dates Will Be Met for post-TMI Requirements for Emergency Operations Facility.Util Will Submit Revised Date After Guidance at 810505 Meeting W/Nrc)
• ML18139B318  + (Responds to NRC Generic Ltr 81-19 Re Potential Reactor Vessel Integrity.Util Will Provide Schedule for Reanalysis or Remedial Action Upon Issuance of Westinghouse Owners Group Program in Late 1981)
• ML18046A669  + (Responds to NRC Generic Ltr 81-19 Re Reactor Vessel Pressurized Thermal Shock.Util Agrees w/C-E Owners Group Indicating No Immediate Safety Concern on Subj Among C-E Plant Owners)
• ML20004B101  + (Responds to NRC Generic Ltr 81-19 Re Thermal Shock to Reactor Pressure Vessel.Westinghouse Owners Group Program, Scheduled for Completion in Dec 1981,will Identify Whether Future Addl Plant Specific Analyses or Actions Are Needed)
• L-81-021, Responds to NRC Generic Ltr 81-21 Re Natural Circulation Cooldown.Forwards Operating Instruction S01-3-6,Revision 1, Plant Operation W/Natural Circulation  + (Responds to NRC Generic Ltr 81-21 Re Natural Circulation Cooldown.Forwards Operating Instruction S01-3-6,Revision 1, Plant Operation W/Natural Circulation)
• ML20207D772  + (Responds to NRC Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping)
• ML20151T354  + (Responds to NRC Generic Ltr 88-01, NRC Position on IGSCC in BWR Austenitic Stainless Steel Piping, Requiring That Licensees Furnish Current Plans Re Pipe Replacement,Insp, Repair & Leakage Detection)
• ML20149J062  + (Responds to NRC Generic Ltr 88-02, Isap II, Dtd 880120. Util Would Consider Participating in Isap II Following Commercial Operation of Plant)
• ST-HL-AE-2824, Responds to NRC Generic Ltr 88-13, Operator Licensing Exams. Requested Estimates of Needs for Operator Licensing Exams for FY89,90,91 & 92 & Anticipated Number of Candidates & Dates Provided  + (Responds to NRC Generic Ltr 88-13, Operator Licensing Exams. Requested Estimates of Needs for Operator Licensing Exams for FY89,90,91 & 92 & Anticipated Number of Candidates & Dates Provided)