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

• ML20042C343  + (Forwards Suppl to Safeguards Portion of Section 5.7.1 of Environ Rept.Any Changes Resulting from Review Will Be Incorporated Prior to Formal Issuance of Section 5.7.1 as Amend to Environ Rept)
• ML13331A868  + (Forwards Suppl to Safety Analysis in 851217 Rev to Proposed Change 136 to Tech Specs,Per 10CFR50.59.Suppl Supports Rev in Number of Detectors in Sphere Encl Bldg Included in Table 3.14.3, Fire Detection Instruments)
• ML17083C062  + (Forwards Suppl to Safety Evaluation & Environ Assessment Providing Evaluation of Wet Reracking Aspects & Boraflex for Spent Fuel Pool Expansion,For Info.No Further Changes to Tech Specs Required.W/O Encl)
• ML20154C345  + (Forwards Suppl to Safety Evaluation Re Electrical Separation Criteria for Separation of Class 1E & non-Class 1E Cables & Raceways.Justification for Less Distance Between Cables than Required by Reg Guide 1.75 Acceptable)
• ML20039H198  + (Forwards Suppl to Safety Evaluation Re New & Spent Fuel Storage Racks,Fuel Handling Sys,Svc Water Sys & Ulitmate Heat Sink & Fire Protection Sys.Suppl Covers Remaining Areas of PSAR)
• ML20002A676  + (Forwards Suppl to Safety Evaluation Re Proposed Fire Protection Mods.Mods Re 3.1.1(1),3.1.5(f) & 3.1.5(j) Are Acceptable.Mods Re 3.1.5(d),3.1.5(k),3.1.6(b) & 3.2.1 Are Unacceptable & Need Addl Mods)
• ML20126L821  + (Forwards Suppl to Safety Evaluation Supporting Response to IE Bulletin 80-11 Re Reevaluation of 22 Masonry Walls, Utilizing Methods Other than Energy Balance Technique)
• ML18047A606  + (Forwards Suppl to Safety Evaluation of SEP Topics II-3.A, II-3.B & II-3.C Reanalyzing Design Basis Surge Level for Facility.Unresolved Differences Now Considered Acceptably Resolved & Topic Reviews Complete)
• ML16152A706  + (Forwards Suppl to Safety Evaluation on Five Listed Items Re Training Program Dealing W/Prevention or Mitigation of Reactor Vessel Voiding.Response to First Four Items Acceptable.Revised Response to Item 5 Requested)
• ML20077H140  + (Forwards Suppl to Schedule Submitted in 830415 Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737, Requirements for Emergency Response Capability, Due to Initial Progress to Satisfy Goal of Implementation in 3 1/2 Yrs)
• ML20094N293  + (Forwards Suppl to Seabrook Station Semiannual Radioactive Effluent Release Rept,Radiological Impact Assessment,1991. Rept Includes Dose Calculations for 1991)
• ML20035D555  + (Forwards Suppl to Seabrook Station Semiannual Radioactive Effluent Release Rept,Radiological Impact Assessment 1992, Including Dose Calculations for Reporting Period)
• ML20070T486  + (Forwards Suppl to Seabrook Station Semiannual Effluent & Waste Disposal Rept, Including Dose Calculations for 1990)
• ML17256A875  + (Forwards Suppl to Section 6.4 to Affect of Thermal Transient on RCS Steam Generator Tube Rupture Incident)
• ML17256A876  + (Forwards Suppl to Section 6.4 to Affect of Thermal Transient on RCS Steam Generator Tube Rupture Incident.)
• ML20238A745  + (Forwards Suppl to Section IV of Environ Radiation Monitoring Program Semiannual Rept 9,Jul-Dec 1976, Per 770105 & 0301 Responses to 761215 Notice of Violation)
• ML20072R390  + (Forwards Suppl to Semiannual Radioactive Effluent Release Rept for Jan-June 1990, Consisting of Revised Quarterly Cumulative Dose Contributions from Radioactive Effluents)
• ML20203B044  + (Forwards Suppl to Semiannual Radioactive Effluent Release Rept,Jan-June 1985, Discussing 850317 Unplanned Liquid Radioactive Effluent Release,Omitted from Original Submittal)
• ML20210D427  + (Forwards Suppl to Semiannual Radioactive Effluent Release Rept for Jul 1991,incorporating Fourth Quarter 1991 Sr-89 & Sr-90 Quantities Detected in Liquid Effluents)
• ML20198N362  + (Forwards Suppl to Semiannual Radioactive Effluent Release Rept,Jul-Dec 1984, Containing Addl Table Designed to Assess Radiation Doses to Hypothetical Worst Case Individual from Reactor Releases for Previous Calendar Year)
• ML20114C502  + (Forwards Suppl to Sept 1983 Monthly Operating Rept.Provides Detailed Descriptions & Effects of Major Changes to Radwaste Treatment Sys.Attachment Update to Changes Reported in Mar 1983 Operating Rept)
• ML18039A873  + (Forwards Suppl to Ser,Approving Amends 259 & 218 to Licenses DPR-52 & DPR-68 Re Approval of 14-day Allowable Outage Time for Emergency Diesel Generators.Suppl Issued to Correct Error Contained in Original SER)
• ML19206B279  + (Forwards Suppl to Ser,Prepared by Core Performance Branch, Concluding That Augmented Startup Program for TMI-2 Is Unnecessary)
• ML20204E471  + (Forwards Suppl to Ser,Summarizing Status of TMI Lessons Learned Items II.B.2,II.F.1,III.D.3.3,I.b.1.2 & II.B.3 & Request for Addl Info)
• ML19220A884  + (Forwards Suppl to Ser.Proposed Irradiation of Test Rods Poses No Safety Concern.Approves Surveillance & post-irradiation Examination to Be Performed & Reported to NRC)

• ML19208B465  + (Forwards Suppl to Status Review of Geologic & Seismologic Data)

• ML19327B945  + (Forwards Suppl to Summary Rept 2 for ASME Section XI Repairs & Replacements Completed from 870901-890519.Rept Includes Certification for Rework of Main Steam Relief Valves & Replacement of MSIV Manifold Piping,Per 890815 Commitment)
• ML20113D511  + (Forwards Suppl to Summary Rept on Oyster Creek Control Room Design Review, Providing Addl Info to Clarify Rept.Schedule Extensions May Be Requested for Certain Commitments Re Cycle 11 Outage Workscope)
• ML20069L753  + (Forwards Suppl to TS Amend Re Pressurizer & Main Steam Safety Valve Lift Setting Tolerances)
• BECO-87-123, Forwards Suppl to Tech Spec 4.3.C.1, Scram Insertion Times, Per NRC Request.Suppl Modifies Util 851115 Proposed Change by Requiring Operable Control Rods to Be Subjected to Scram Time Test After Reactor Shutdown  + (Forwards Suppl to Tech Spec 4.3.C.1, Scram Insertion Times, Per NRC Request.Suppl Modifies Util 851115 Proposed Change by Requiring Operable Control Rods to Be Subjected to Scram Time Test After Reactor Shutdown)
• ML19206A928  + (Forwards Suppl to Testimony of CA Lovejoy W/Accompanying Affidavit)
• L-84-284, Forwards Suppl to Util 840928 Response to NRC 840813 Request for Addl Info Re Proposed Amend to Spent Fuel Storage Facility Expansion.Changes Involve Item 1.3 on Region 2 Racks,Summary of Design Stresses & Min Margins of Safety  + (Forwards Suppl to Util 840928 Response to NRC 840813 Request for Addl Info Re Proposed Amend to Spent Fuel Storage Facility Expansion.Changes Involve Item 1.3 on Region 2 Racks,Summary of Design Stresses & Min Margins of Safety)
• ML19260D065  + (Forwards Suppl to Util Providing Info Re Implementation of Lessons Learned Task Force Category a Items.Submits Info Re Emergency Power Supply,Diverse Containment Isolation & post-accident Sampling)
• 3F0788-12, Forwards Suppl to Util Re Emergency Feedwater Leaks & Summary of Presentation During 880708 Meeting in Rockville,Md,Per 880706 Confirmation of Action Ltr. Corrective Actions Associated W/Stated Insp Rept  + (Forwards Suppl to Util Re Emergency Feedwater Leaks & Summary of Presentation During 880708 Meeting in Rockville,Md,Per 880706 Confirmation of Action Ltr. Corrective Actions Associated W/Stated Insp Rept)
• ML20031C477  + (Forwards Suppl to Util Re IE Bulletin 80-06, ESF Reset Controls. Suppl Describes Revisions & Deletions to Proposed Mods in 810617 Response Resulting from Recent Design Review)
• RBG-21-403, Forwards Suppl to Util Re Insp & Mod Repts for Facility Tdi Standby Diesel Generators.End Revises Notes Pages & Applicable Entries in Rept to Further Clarify Various Items  + (Forwards Suppl to Util Re Insp & Mod Repts for Facility Tdi Standby Diesel Generators.End Revises Notes Pages & Applicable Entries in Rept to Further Clarify Various Items)
• ML19220B907  + (Forwards Suppl to on Deficiency in Const Involving Below Std Concrete.Action Is Now Complete)
• ML20236B731  + (Forwards Suppl to post-exercise Assessment of Remedial Activities Performed as Result of Deficiencies Noted at 860604 Exercise at Plant.Tables Updated to Provide More Complete Picture of Exercise Activity)
• ML20093N203  + (Forwards Suppl to to ASLB & Aslab Re NRC Duties Concerning Supplemental Water.Related Correspondence)
• ML20093N251  + (Forwards Suppl to to ASLB & Aslab Re NRC Duties Concerning Supplemental Water.Certificate of Svc Encl. Related Correspondence)
• ML20012F034  + (Forwards Suppl to, Semiannual Radioactive Release Rept Initial Plant Startup Through Fourth Quarter 1989, Consisting of Dose Calculations)
• ML20012F035  + (Forwards Suppl to, Semiannual Radioactive Release Rept Initial Plant Startup Through Fourth Quarter 1989, Consisting of Dose Calculations)
• ML17313A578  + (Forwards Supplement 1 to Special Rept 1-SR-98-001.Supplement Provides Results of SG Tube ISI That Was Performed During Seventh Refueling Outage)
• ML20137D896  + (Forwards Supplement 7 to 970129 License Amend Request Re Cooling Water Sys Emergency Intake Design Bases)
• ML20137D901  + (Forwards Supplement 7 to 970129 License Amend Request Re Cooling Water Sys Emergency Intake Design Bases)
• ML20137P772  + (Forwards Supplement 8 to Final Rept CENPD-279, Annual Rept on Abb CE ECCS Performance Evaluation Models, Per 10CFR50.46)
• ML20137P770  + (Forwards Supplement 8 to Final Rept CENPD-279, Annual Rept on ABB CE ECCS Performance Evaluation Models, Per 10CFR50.46)
• ML20101U415  + (Forwards Supplement to 10CFR50.59 Annual Rept for Period Ending 920331.Supplement Consists of Summary of 10CFR50.59 Safety Evaluation for Core Operating Limits Rept Revs)
• ML19305E313  + (Forwards Supplement to 790924 Response Re IE Insp Rept 50-553/79-12 & Noncompliance Item 553/79-12-01,per NRC 800325 Request.Rockwell Intl Notified That Future Work Performed Using Insp Procedures W/Proper Signature Affixed)
• ML18058A304  + (Forwards Supplement to 910909 Request for Relief from ASME Boiler & Pressure Vessel Code to Repair Containment Air Cooler Cooling Coils,Per 920311 Telcon W/Nrc)
• ML20114D922  + (Forwards Supplement to 910930 Response to NRC Request for Addl Info to Resolve 920618 Telcon Request for Relief from Inservice Insp Program.Justification Re Removal of Insulation Panels from Bracket Welds Encl)