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A list of all pages that have property "Title" with value "Modified Question Source Information". Since there have been only a few results, also nearby values are displayed.

Showing below up to 28 results starting with #1.

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List of results

  • ML20262C299  + (Modified MRS Facility Receiving & Handling Facility Basement Plan)
  • ML20262C304  + (Modified MRS Facility Receiving & Handling Facility Ground Level Plan)
  • ML20262C365  + (Modified MRS Facility Receiving & Handling Facility Scheme 4 Sections)
  • ML20262C286  + (Modified MRS Facility Receiving & Handling Facility Second Level Plan)
  • ML20262C309  + (Modified MRS Facility Receiving & Handling Facility Second Level Plan)
  • ML20262C294  + (Modified MRS Facility Receiving & Handling Facility Sections)
  • ML20262C318  + (Modified MRS Facility Receiving & Handling Facility Sections)
  • ML20262C290  + (Modified MRS Facility Receiving & Handling Facility Third Level Plan)
  • ML20262C313  + (Modified MRS Facility Receiving & Handling Facility Third Level Plan)
  • ML20198N772  + (Modified NPDES Permit IL0005037,issued to Commonwealth Edison Co)
  • ML20197D234  + (Modified NPDES Permit IL0005037,issued to Commonwealth Edison Co)
  • ML20010B727  + (Modified NPDES Permit IL0048313,issued to Comm Ed.Util Ltrs to Il EPA Encl)
  • ML20154C206  + (Modified NPDES Permit IL0048313,issued to Comm Ed)
  • ML20213A692  + (Modified NPDES Permit IL0048313,issued to Comm Ed)
  • ML20214E305  + (Modified NPDES Permit WI-0000957-3,issued to Wisconsin Electric Power Co)
  • ML22138A145  + (Modified NPDES Permit for Storm Water Retention Pond)
  • ML22138A147  + (Modified NPDES Permit for Storm Water Retention Pond)
  • ULNRC-06746, Modified NPDES Permit for Storm Water Retention Pond  + (Modified NPDES Permit for Storm Water Retention Pond)
  • ML20196C911  + (Modified Notice of Consideration of Issuance of Amends to Licenses DPR-53 & DPR-69 & Opportunity for Hearing on 881025 Request to Modify 880609 Application to Reduce Max Limit for Keff from 0.98 to 0.95)
  • IR 05000255/1992003  + (Modified Operational Safety Team Insp Rept 50-255/92-03 on 920106-10.Major Areas Inspected:Engineering/Technical Support,Maint,Safety Assessment/Quality Verification & Operations)
  • ML20004G099  + (Modified Organization Plan,Figure 15.6.2-2)
  • ML19340D081  + (Modified Page 2 of Chairman Ahearne Separate Views Contained in 801205 Memorandum & Order Re Treatment of Psychological Stress Issue in TMI-1 Restart Proceeding)
  • 3F0404-11, Modified Proposed License Condition, License Amendment Request 280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System  + (Modified Proposed License Condition, License Amendment Request 280, Revision 1, Revised Improved Technical Specification (ITS) 3.7.9, Nuclear Services Seawater System)
  • ML20216D943  + (Modified Proposed TS Pages Re 980324 Request for Amends to Licenses NPF-37 & NPF-66)
  • ML20244B118  + (Modified Proposed Tech Specs 3/4.6.1.1, Primary Containment & 3/4.6.5.1, Secondary Containment, Listing Devices Affected by Proposed Changes)
  • ML19253B826  + (Modified Proposed Tech Specs for Overpressure Protection Sys)
  • ML19209C475  + (Modified QA Program for Operations)
  • ML20350B785  + (Modified Question Source Information (Post 2020 Audit) (Folder 3))
  • ML20325A031  + (Modified Questions for ADAMS Record)
  • L-17-292, Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule  + (Modified RT PTS Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule)
  • ML17254A850  + (Modified Rack Installation Handling and Equipment. No Rev Date)
  • ML20059G717  + (Modified Reactor Requalification Program for Afrri Triga Reactor Facility)
  • ML20212M425  + (Modified Rev 0 to Procedure EIP-24, Test Procedure for Performance Isolation of 1E Analog & Digital Isolators)
  • ML20265B890  + (Modified Source Mount Assembly)
  • ML18017B763  + (Modified Steam Break Protection Process Control Block Diagram. Sheet 22)
  • ML19305E704  + (Modified Subspace Computation for Eigenvalues & Eigenvectors)
  • ML20055B706  + (Modified Tech Spec on Supervisory Authority Re Radiological Control Technician Training)
  • ML20125D614  + (Modified Tech Specs 3.3.3.9 (Table 3.3-12) & 3.7.11.3, Deleting Ref to Fire Protection of River Water Structure & 3.7.11.6 (Tables 3.7-5 & 3.7-6 & Bases 3/4.7.11),adding Specs from re-evaluation)
  • ML19253C970  + (Modified Tech Specs Change 23,changing Table 3.6-1 to Add Automatic Valves 1-1A-55 & TV-1A-102B & Deleting Valve TV-102A)
  • ML20081F987  + (Modified Tech Specs for Design Features Re Reactor Core Fuel Assemblies & Design Pressure & Temp.Significant Hazards Consideration Determination Encl)
  • ML20041E939  + (Modified Waste Disposal Sys for San Miguel Mill Project)
  • ML24012A005  + (Modified from the Diablo Canyon Power Plant License Renewal Application, Figures)
  • ML17223B367  + (Modifies & Supersedes Re Bulletin 88-011, Pressurizer Surge Line Thermal Stratification)
  • ML19261A408  + (Modifies 781220 Request to Change AR Nuclear One Unit 2 Tech Spec Tables 2.2-1&3.3-4.Changes Involve Low Pressurizer Pressure & Low Steam Generator Pressure Trip Setpoints)
  • ML18082B295  + (Modifies 790112 Commitment Re Storage of Air Breathing Units & Spare Cylinders.Ten Scott SCBAs Will Be Located at Radiological Control Point to Svc Entire Controlled Access Area)
  • ML19259C852  + (Modifies 790606 Response to IE Bulletin 79-03 Re Longitudinal Weld Defects.Discusses Use of Gas Strippers & Regenerative Heat Exchangers Mfg by Youngstown Welding & Engineering Co)
  • ML20078D235  + (Modifies 791109 Commitment for Nuclear Support Svcs Dept to Perform Multiple Equipment Failure Analysis.Plant Staff, Rather than Nuclear Support Svcs Dept,Will Perform Review)
  • ML19294B516  + (Modifies 791210 Request for Amend to License R-63.Reactor Area Monitors,Stack Monitors Daily Air Sample Taken in Bay Will Be Discontinued.Radiation & Contamination Survey of R-3 Bay Area Will Be Conducted Quarterly)
  • ML19331D321  + (Modifies 800814 Response to IE Bulletin 80-16 Re Potential Misapplication of Certian Rosemount Models 1151 & 1152 Pressure Transmitters.Four 1152 GP Transmitters Used W/A Output Code)
  • ML19350F094  + (Modifies 801001 Response to IE Bulletin 80-05, Vacuum Condition Resulting in Damage to Chemical Vol Control Sys (CVCS) Holdup Tanks. Reactor Coolant Pump Seal Drain Tanks Have Vacuum Breakers & Nitrogen Gas Sys.Design Change Set)
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