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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

• ML20072H421  + (Clarifies Re Status of Conditionally Admitted Contentions I.33(G) & 33(L))
• ML20039B040  + (Clarifies Re Status of Fire Protection Requirements.Msiv & Battery Rooms Should Be Added to Tech Specs.Tech Specs Amend Request Will Be Submitted to Correct Listed Discrepancies)
• ML20024C806  + (Clarifies Re Turbine Sys Maint Program Options for Resolution of SER Open Item 2 on Turbine Missiles)
• ML18085A214  + (Clarifies Re Upgrading of Emergency Support Facilities.Requirements for Technical Support Ctr & Emergency Operations Facility Will Be Implemented in Accordance W/Nrc Schedules)
• ML20132E320  + (Clarifies Re Use of ASME Code Cases N-397 & N-411.Ltr Gave Generic Approval Provided Listed Items (a) Through (F) Implemented.Response to Whether CP Amend Needed Requested)
• TXX-3092, Clarifies Re Violation of Piping Min Wall Thickness,Reported Per 10CFR50.55(e).Attached Rept Intended to Be Classified as Interim.Will Submit Progressive Repts as Welds Are Dispositioned Through Engineering Review  + (Clarifies Re Violation of Piping Min Wall Thickness,Reported Per 10CFR50.55(e).Attached Rept Intended to Be Classified as Interim.Will Submit Progressive Repts as Welds Are Dispositioned Through Engineering Review)
• ML19253B467  + (Clarifies Re Violations Noted in IE Insp Rept 50-258/79-28.Corrective Actions:Requested Gasket Supplier to Obtain Certificate Stating That SCE-43 Matl Conforms to ASTM D 1056)
• ML17053C483  + (Clarifies Reasons for NRC 801126 Enforcement Actions. Results of Investigation Determined That Perkins Possess Necessary Character & Reliability to Be Reinstated in Nuclear Industry.Order Withdrawing Show Cause & Mods Encl)
• ML20052B700  + (Clarifies Reasons for Plugging Three Steam Generator Tubes Per Encl Description to Util Ltr W3K-82-0092 & Two Addl Tubes w/through-wall Discontinuity Indications)
• NUREG-0582, Clarifies Reasons to Proceed W/Development of Preliminary Calculational Tool for Steam Bubble Induced Water Hammer. Proposed Use Need Is Essential Adjunct to Efforts in Resolving Water Hammer Task.Graphs Encl  + (Clarifies Reasons to Proceed W/Development of Preliminary Calculational Tool for Steam Bubble Induced Water Hammer. Proposed Use Need Is Essential Adjunct to Efforts in Resolving Water Hammer Task.Graphs Encl)
• ML20137S018  + (Clarifies Recent Ltr Re Revised Criteria for Training & Experience for Medical Users of Byproduct Matl.Physician May Submit Application Listing Specific Qualifications for NRC Review & Authorization to Use Radiopharms.Fr Notice Encl)
• ML19210D298  + (Clarifies Recent Press Releases Re Current Planning for Facility.Addl Major Expenditures for Plant Should Be Deferred,Based on Unstable Climate Concerning Nuclear Plant Licensing)
• ML20057C955  + (Clarifies Recent Telcon Re Nrc/Epri Technical Meeting During Wk of Oct 11 & Possibly Offer Suggestions for Development of Agenda)
• ML20070Q228  + (Clarifies Reclassification of Fort Calhoun Station Warehouse Storage from ANSI N45.2.2 Level a Criteria to Level B Criteria)
• ML20207Q164  + (Clarifies Recommendation That Policy Be Established to Routinely Delete Names & Other Identifying Info Concerning Persons That Provide Info to Nrc.Recommendation Pertains to Cases Where Confidentiality Not Granted)
• ML19347C770  + (Clarifies Record Re 750224 AO 75-7 Re Defective Emergency Condenser Outlet Pipe,Astm Min Wall Criterion May Have Been Violated.Concludes That Corrective Action Taken,Piping Replacement,Remains Adequate)
• ML13322B184  + (Clarifies Record Re Reactor Coolant Pump Trip Requirements. Analysis Shows That RCS Response Not Significantly Affected by Operation or Tripping of Pumps During Design Basis Events Requiring Safety Injection)
• ML20032B234  + (Clarifies Record Re Wi Environ Decade .Licensee Was Not Challenge to ASLB Jurisdiction But Was Submitted to Expedite Matters Properly Before Aslb.Related Correspondence)
• ML19343B654  + (Clarifies Redrafted Doherty Contention 26 Re Stud Bolts)
• ML20116P031  + (Clarifies Ref 1 in Util Re Final Draft Combined Ts,In Response to NRC 920903 Request.Certification Includes Validation of Remaining Bracketed Info in Final Draft of Combined TS)
• ML15244A308  + (Clarifies Ref to Order Stating That Implementation of SPDS Complete.Review of SPDS Still Ongoing & Has Not Yet Been Resolved)
• ML20127B519  + (Clarifies Region I Ofc View of Allegation RI-89-A-0072, Adjustment of Molded Case Circuit Breakers (MCCB) at Susquehanna)
• ML20137R520  + (Clarifies Region III Position Re Proposed Rev to 10CFR35. Publication After Modifying Section 35.36 to Require That Applicants & Licensees Submit Changes to Radiation Safety Program Which Decrease Effectiveness Preferred)
• ML20127A309  + (Clarifies Relationship Between Emergency Response Facilities & SPDS Completion Schedules.Interim Method,Providing Required Info to New Facility Until SPDS Complete,Described)
• ML20150E206  + (Clarifies Relevant Issues Raised in LC Clark Re Recent Filings by J Doe.W/Supporting Info & Certificate of Svc)

• ML20094L956  + (Clarifies Relief Request I2R-15 Submitted W/Isi Program)

• ML20247L357  + (Clarifies Remark Re Discharge Through Existing Ventilation Stack to Avoid Confusion.Remark Was in Response to Question Re Purpose of Dismantlement & Replacement of Existing Ventilation Stack)
• ML20154E797  + (Clarifies Repair Schedule Provided on 871118 for Inoperability of Remote Shutdown Panel Source Range Neutron Flux Instrument NI-9.Estimated Time for Repair Revised to 3 Days)
• ML20010G371  + (Clarifies Reportability of Equipment Failures Discovered During Modes of Operation When Equipment Not Required to Be Operable.Tech Spec Change Not Required)
• ML20215E666  + (Clarifies Reportability of RCIC Inoperability,Per 10CFR50.72 & 50.73.Licensee Response Following 860905 Event Not Reportable Provided That Licensee Did Not Take Credit for RCIC as ESF or in Safe Shutdown Analysis)
• ML20245C877  + (Clarifies Request FOIA-89-112.Requests Documents That Support Designation of Cesium Chloride Capsules,Mfg at DOE Hanford Waste Encapsulation & Storage Facility in Richland, Wa,As Sealed Sources)
• ML20064J557  + (Clarifies Request for Addl Info Re IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety-Related Sys Components by Asiatic Clams & Mussels)
• GO2-85-656, Clarifies Request for Amend to Tech Spec 3/4.6.4 Re Suppression chamber-drywell Vacuum Breakers.Analysis on Opening Time Response Completed.Tech Spec Changes Not Effected.Amend Request Should Be Processed  + (Clarifies Request for Amend to Tech Spec 3/4.6.4 Re Suppression chamber-drywell Vacuum Breakers.Analysis on Opening Time Response Completed.Tech Spec Changes Not Effected.Amend Request Should Be Processed)
• ML20153F186  + (Clarifies Request for Amends to Licenses DPR-71 & DPR-62, Changing Tech Specs Re Turbine Stop Valve Surveillance Requirements,By Superseding 850506 Discussion & Significant Hazards Consideration)
• ML20073A045  + (Clarifies Request for Exemption from Requirements of 10CFR50,App R,Section III for AFW Pump Room)
• ML20066E079  + (Clarifies Request for Exemption from Requirements of Generic Ltr 90-08 Re Simulator Certification & Annual Operating Exam.Simulator Certification Rept Will Be Submitted No Later than 920131 & Exams Scheduled for End of Oct 1991)
• ST-HL-AE-1577, Clarifies Request for Exemption to GDC 4 to Eliminate Postulated Breaks in RCS Piping.Request Does Not Apply to Containment Design Basis,Eccs,Esf Sys Response or Design of RCS Heavy Component Supports  + (Clarifies Request for Exemption to GDC 4 to Eliminate Postulated Breaks in RCS Piping.Request Does Not Apply to Containment Design Basis,Eccs,Esf Sys Response or Design of RCS Heavy Component Supports)
• ML18018B627  + (Clarifies Request for Extension of CP in Support of Const Schedule Reported in 840123 Const Status Rept.Util Firmly Committed to June 1985 Fuel Load Date)
• ML17277A797  + (Clarifies Request for Full Power 40 Yr Ol.Fuel Load Planned for Nov 1983,w/commercial Operation by May 1984)
• ML13333A502  + (Clarifies Request for Relief from Inservice Insp Requirements of ASME Boiler & Pressure Vessel Code,Section Xi.Indicates Typographical Errors in NRC Safety Evaluation)
• ML20117P286  + (Clarifies Requesting Administrative Change to Unit 2 TSs by Deleting Ref to cycle-specific L* Criteria)
• ML20073S172  + (Clarifies Requests for Exemptions from 10CFR50.48 & App R Requirements in Response to NRC Request at 830330 Meeting. Rev to 820701 Response to Be Submitted by 830530)
• ML20213F105  + (Clarifies Requirement for Licensees to Rept Event or Condition That Results in Multiple Failures of Reactor Protection Sys to Headquarters Operations Ctr.Guidance to Rules Provided in NUREG-1022,10CFR50.72 & 50.73)
• ML19211A097  + (Clarifies Requirements Re Control Rod Position Indication Sys at Westinghouse Pwr,Due to Existing Wide Variations of LERs Received)
• ML20003J254  + (Clarifies Requirements of Generic Ltrs Issued Subsequent to Accident & Informs of Plans for Processing Future Generic Ltrs.List of Generic Ltrs Issued Since TMI-2 Accident Encl)
• ML20076G274  + (Clarifies Resolution of NUREG-0612, Control of Heavy Loads. Statement Re Repairs Amended to Read Any Repairs Will Be Performed in Accordance W/Calvert Cliffs Plant Procedures)
• ML20045H548  + (Clarifies Resolution of Previously Expressed Concern Re Funding of Major Reactor Facility Repair.Funding Route for Specific Large Budget Repair Items Currently in Use Will Continue to Be Available)
• ML20009A176  + (Clarifies Responding to 810519 Second Request for Production of Documents.Documents Responsive to Paragraphs 1,2 & 3 Are Available in Pdr.Documents Responsive to Paragraphs 4-9 Will Be Produced Later)
• ML20008F901  + (Clarifies Response to 10CFR50.34(e) Provided in PSAR Amend 43 Per 810506 Request.Test Date & Analysis Will Include Igniter Performance & Endurance Characteristics If Option Chosen Continues to Be Deliberate Ignition Sys)
• ML20215D075  + (Clarifies Response to 860804 Miscellaneous Amends Re Physical Protection of Nuclear Power Plants,Per Generic Ltr 87-08.Rev 10 to Security Plan Contained Changes Addressed Under 10CFR50.54(p) & Required by Rulemaking Process)
• ML20235G797  + (Clarifies Response to 870824 RII-87-07-01-SL4 Notice of Violation.Corrective Actions:Procurement of 8-inch Schedule 160 Calibr Block Initiated)