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A list of all pages that have property "Title" with value "Proposed Tech Spec Revisions Re Administrative Changes". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20082T482  + (Proposed Tech Spec Rev Re Use of H-451 Graphite in Fuel Rods.Significant Hazards Consideration Analysis Encl)
  • ML20071C388  + (Proposed Tech Spec Rev Renumbering Mechanical Snubbers on Table 3.6-lb for Clarity,Adding Sixteenth Snubber & Changing Emergency Preparedness Audit Frequencies)
  • ML20129A841  + (Proposed Tech Spec Rev to Page 6-24,adding Continuous Surveillance by Qualified Individual as Alternative to Routine Radiation Work Permit Procedure in High Radiation Area)
  • ML20070E230  + (Proposed Tech Spec Rev to Section 6.0 Re Administrative Controls Covering Min Shift Crew Composition & Unit Staff Qualifications)
  • ML20087L475  + (Proposed Tech Spec Rev to Table 3.8-2, Motor Operated Valves Thermal Overload Protection &/Or Bypass Devices)
  • ML20107F221  + (Proposed Tech Spec Rev,Deleting Limiting Condition for Operation Re Auxiliary Feedwater Sys & Clarification of Inservice Insp Requirements for Steam Generators)
  • ML20009H267  + (Proposed Tech Spec Revised Pages 1.1/2.1-4,1.1/2.1-5, 1.1/2.1-6,1.1/2.1-7,1.1/2.1-11,1.2/2.2-1,1.2/2.2-2, 3.3/4.3-5,3.3/4.3-10,3.5/4.5-10,3.5/4.5-14,3.5/4.5-14a, 1.1/2.1-7a,1.2/2.2-2a,3.5/4.5-146 & Figures 3.5-1)
  • ML20138K612  + (Proposed Tech Spec Revising 4.10.1, Inservice Insp of Steam Generator Tubes, to Allow Sleeving as Means to Repair Steam Generator Tubes & Include Pitting as Mechanism Causing Tube Degeneration)
  • ML20100C492  + (Proposed Tech Spec Revising Containment Pressure Setpoint & Deleting MSIV Surveillance)
  • ML20197H038  + (Proposed Tech Spec Revising Inservice Insp & Inservice Testing Requirements of Section 4.3 to Reflect NRC Recommended Wording for Requirements)
  • ML18142A355  + (Proposed Tech Spec Revising Limiting Condition for Operation & Surveillance Requirements for Reactor Trip Bypass Breakers & Undervoltage & Shunt Trip Logic)
  • ML17213B033  + (Proposed Tech Spec Revising Linear Heat Rate Prior to Unit Restart Following Upcoming Refueling Outage)
  • ML20212A536  + (Proposed Tech Spec Revising Reporting Requirements for Semiannual Effluent Release Rept.Certificate of Svc Encl)
  • ML17262A787  + (Proposed Tech Spec Revising Section 6.5.1 Re Plant Operations Review Committee Function)
  • ML20237E010  + (Proposed Tech Spec Revising Tables 3.3.5.2-1 & 4.3.5.2-1 to Change Instrument Tag Numbers to Comply w/10CFR50,App R)
  • ML20080J043  + (Proposed Tech Spec Revising Titles for Plant Safety Review Committee)
  • ML20070E541  + (Proposed Tech Spec Revising Visual Exam,Visual Exam Acceptance Criteria & Functional Testing of Snubbers)
  • ML20094M350  + (Proposed Tech Spec Revision Consisting of Table of Contents)
  • ML20010E141  + (Proposed Tech Spec Revision Pages 15.3.6-2,15.3.6-3, 15.4.4-12,15.4.4-15 & 15.4.4-15a Re Testing of Containment Purge Supply & Exhaust Sys Isolation Valves)
  • ML16148A442  + (Proposed Tech Spec Revision Re Core Protection Safety Limits Protective Sys Max Allowable Setpoints & Rod Position Limits)
  • ML20003D687  + (Proposed Tech Spec Revision Re Tables 3.6-2,3.7-4a, 3.7-4b & 3.8-1 Concerning Containment Isolation Valves, safety-related Hydraulic & Mechanical Snubbers & Containment Penetration Conductor Overcurrent Protective Devices)
  • ML19340A249  + (Proposed Tech Spec Revisions)
  • ML20053A693  + (Proposed Tech Spec Revisions Changing 8-h/month Time Constraint for One Channel of Power Source Monitoring Sys for Inservice RPS M-G Set or Alternative Source to as Necessary)
  • ML20069Q480  + (Proposed Tech Spec Revisions Changing Duration of Containment Integrated Leak Rate Test from 24-h to 8-h. Justification for Proposed Revisions Encl)
  • ML20070F256  + (Proposed Tech Spec Revisions Correcting Administrative Inconsistency Re Min Number of Operable Channels Per Trip Sys Requirements for Certain HPCI & RCIC Sys Isolation Actuation Instruments)
  • ML20058E293  + (Proposed Tech Spec Revisions Re Administrative Changes)
  • ML16134A676  + (Proposed Tech Spec Revisions Re Reload Design Calculations for Cycle 7)
  • ML19317E779  + (Proposed Tech Spec Revisions for Reactor Operation W/Two Reactor Coolant Pumps)
  • ML19318A631  + (Proposed Tech Spec Revisions for safety-related Sys.Change Justifications Encl)
  • ML20009F897  + (Proposed Tech Spec Revisions to Reflect Corporate Organizational Changes,Plant Organizational Changes & Changes in Plant Nuclear Safety Committee)
  • ML19312C911  + (Proposed Tech Spec Revisions to Support Cycle 2 Operation)
  • ML18025B642  + (Proposed Tech Spec Revisions to Table 3.5.I-1,2,3,4&5 Re Extending Exposure Range of Fuel Presently Loaded in Core. Justification & Safety Analysis Encl)
  • ML19305E090  + (Proposed Tech Spec Revisions,Allowing Conduct of Short Containment Integrated Leak Rate Test)
  • ML20066D284  + (Proposed Tech Spec Revisions,Allowing Operation Up to 30 Days W/One Temp Switch in Main Steam Tunnel Inoperable)
  • ML20072H501  + (Proposed Tech Spec Revs Re Frequency of Steam Generator Inservice Insp)
  • ML17324A959  + (Proposed Tech Spec Revs Re Inservice Insp & Testing Requirements,Boric Acid Transfer Pumps,Auxiliary Feedwater Pumps & Centrifugal Charging Pumps)
  • ML20116K634  + (Proposed Tech Spec Revs Re Min Critical Power Ratio Values, MAPLHGR Values for New Fuel Type BP8DRB299,addl MAPLHGR Values for Fuel Types P8DRB285,P8DRB265H & P8DRB299 & Deletion of Ref to Old 8X8 Fuel Type Removed from Core)
  • ML20078E649  + (Proposed Tech Spec Revs Reanalyzing Worst Large Break LOCA Case Using Initial Fuel Rod Conditions Determined from Currently Approved PAD Fuel Thermal Safety Model.Attachments B-H Encl)
  • ML18025B985  + (Proposed Tech Spec Revs for Reload 5,Cycle 6 Operation)
  • ML20107A001  + (Proposed Tech Spec Revs to Sections 3.13 & 4.13 to Incorporate Requirements of Accident Monitoring Instrumentation,Per NUREG-0737 & Generic Ltr 83-36 & Clarify Table 3.13.1 Re Format of Relief Valve Position Indicators)
  • B11549, Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement  + (Proposed Tech Spec Revs to Sections 5 & 3/4.9,expanding Storage Capacity of Spent Fuel Pool from 667 to 1,112 Storage Locations by Reracking Spent Fuel Pool W/Combination of Poison & Nonpoison Racks in Two Region Arrangement)
  • B12000, Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks  + (Proposed Tech Spec Revs,Expanding Storage Capacity of Spent Fuel Pool by Storing Consolidated Spent Fuel in Fuel Storage Racks)
  • ML20081J154  + (Proposed Tech Spec Revs,Incorporating New Requirements for Radiological Effluent Monitoring,Recording & Reporting in Accordance w/NUREG-0473.Description & Justification for Changes & Significant Hazards Consideration Encl)
  • ML18031A874  + (Proposed Tech Spec Revs,Incorporating New Requirements for Radiological Effluent Monitoring,Recording & Reporting Per NUREG-0473)
  • ML18092A758  + (Proposed Tech Spec Revs,Reflecting Increase in Rated Thermal power.Marked-up Draft FSAR Changes Encl)
  • ML20072H332  + (Proposed Tech Spec Revs,Requiring Annual Rept of Main/Steam Safety/Relief Valve Actuations,In Response to NUREG-0737, Item II.K.3.3 & Generic Ltr 83-02)
  • ML20034H341  + (Proposed Tech Spec SR 4.8.1.1.2.h(2),reflecting Deletion of Requirements That Requires Pressure Test of Portions of Diesel fuel-oil Sys Designed to Section Iii,Subsection Nd of ASME Code)
  • ML20093N898  + (Proposed Tech Spec SR 5.3.12, Steam Generator Tube Leaks Surveillance)
  • ML20094B374  + (Proposed Tech Spec SRs 4.7.6.c,d & E,Reflecting Proposed Design Change to Output Rating of Charcoal Filter Adsorber Unit Heater in Pressurization Sys Portion of CR Emergency Ventilation Sys)
  • ML20216F622  + (Proposed Tech Spec Section 1.3(2),reflecting Addition of Neutron Guide Hall Adjacent to Reactor Bldg for Conducting Cold Neutron Research.Facility Description & Safety Analysis Encl)
  • ML20065E810  + (Proposed Tech Spec Section 15.3.2, Chemical & Vol Control Sys, Eliminating Necessity of High Concentration Boric Acid & Removing Operability Requirements for Associated Heat Tracing)
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