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List of results

• 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)
• ML21327A342  + (Modified Question Source Information)
• ML23247A002  + (Modified Question Source Information)
• ML23356A148  + (Modified Question Source Information)
• ML23334A220  + (Modified Question Source Information)
• 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)
• ML19341C766  + (Modifies 801209 Response to NRC Re Deviations Noted in QA Program Insp Rept 99900501/80-01.Deficiencies Noted in Interface Control Logs Will Be Corrected by 810331)
• ML20009G266  + (Modifies 801229 Commitment to IE Bulletin 80-23, Failures of Solenoid Valves Mfg by Valcor Engineering Corp. Only Valve Coils Will Be Replaced Rather than Entire Valve)
• ML20010C749  + (Modifies 810330 Response to Generic Ltr 81-10 Re post-TMI Requirements for Emergency Operations Facility.Discusses Delayed Schedule for Implementing Staffing Levels of Table B-1 of NUREG-0654,Revision 1)
• ML18051B343  + (Modifies 820526 Commitment by Clarifying Applicability of Rept of Oil,Salt or Polluting Loss to NPDES Permit,Per Tech Spec 3.2.NPDES Permit Violations & Matl Loss Repts Will Be Submitted Semiannually)
• ML20115E915  + (Modifies 840511 Response to Generic Ltr 84-04.Partial Exemption to GDC 4 Should Be Granted for First Two Cycles of Operation.Relief for Postulated Loop Break Effect on Reactor Cavity Will Be Pursued in GDC 4 Rulemaking)
• U-600351, Modifies 841119 Description of Automatic Depressurization Sys (ADS) Accumulator Low Pressure Alarm.Common Annunciator Will Indicate Low Pressure Condition in ADS Accumulators But Accumulator Cannot Be Identified at Plant Computer  + (Modifies 841119 Description of Automatic Depressurization Sys (ADS) Accumulator Low Pressure Alarm.Common Annunciator Will Indicate Low Pressure Condition in ADS Accumulators But Accumulator Cannot Be Identified at Plant Computer)
• ML20213F201  + (Modifies 860421 Instructions Re Adjustments to Reconcile Licensee Records W/Nuclear Matl Mgt & Safeguards Sys (Nmmss).Adjustments Will Be Sent to NMSS by 860731,per 860611 Telcon)
• ML20215K245  + (Modifies 860924 & 1007 Confirmatory Action Ltrs 86-12,per 861011 Telcon.Startup Authorized to Conduct Tests Delineated in)
• ML20211A181  + (Modifies 860924 Confirmatory Action Ltr 86-12,per 861006 Telcon.Restart to Conduct Hot,Critical & Loss of Power Tests Authorized.Meeting W/Region I Staff Will Be Held Prior to Any Subsequent Startup)
• ML20034A193  + (Modifies 900316 Request That Util Submit Initial Version of Business Plan by End of Jul 1990,based on Diagnostic Evaluation Team Rept.Plan Will Be Developed in Successive Stages Over Next 12 to 18 Months)
• ML17329A381  + (Modifies 910225 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Re Missed Surveillances Per Generic Ltr 87-09 as Result of NRC Request)