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List of results

• ML20155D982  + (Forwards Rev 0 to GE-NE-B13-01980-24, Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station)
• ML20100L344  + (Forwards Rev 0 to GE-NE-B1301786-01, LaSalle Unit 2 RPV Surveillance Matls Testing & Analysis & Rev 0 to GE-NE-B1301786-02, Demonstration of Compliance W/10CFR50, App G for LaSalle Unit 2 Plate Matl)
• ML20205R532  + (Forwards Rev 0 to GE-NE-T43-00002-00-03, BWROG Position on Use of SRVs & LP Sys as Redundat SS Paths, Dtd Mar 1999. BWROG Requests That NRC Conclude,On Basis of Screening of Substantive Info Provided,That Generic Issue May Exist)
• ML20035D481  + (Forwards Rev 0 to GGNS-MS-48.0, Grand Gulf Nuclear Station COLR,Safety-Related)
• ML20097F255  + (Forwards Rev 0 to GL 95-07, Pressure Locking & Thermal Binding of Power-Operated Gate Valves)
• ML20205C896  + (Forwards Rev 0 to Generic Hydrogen Control Info for BWR/6 Mark III Containments, Per Guidelines of NUREG-0390.Final Rept Will Add Listed Info on Generic Items of Hydrogen Control Owners Group Program Plan Currently in Progress)
• ML17264B106  + (Forwards Rev 0 to Ginna Station Colr,Cycle 27, Per TS 5.6.5)
• ML17264B107  + (Forwards Rev 0 to Ginna Station Colr,Cycle 27, Per TS 5.6.5)
• ML20087D736  + (Forwards Rev 0 to Giraffe Sys Interaction Test Specification)
• ML20137H999  + (Forwards Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept. Effects of Safety Relief Valve Hydrodynamic Loads Adequately Covered in Original Plant Design.Substantial Margins in Discharge Loads Exist)
• AECM-85-0266, Forwards Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept. Effects of Safety Relief Valve Hydrodynamic Loads Adequately Covered in Original Plant Design.Substantial Margins in Discharge Loads Exist  + (Forwards Rev 0 to Grand Gulf In-Plant Safety Relief Valve Test Final Rept. Effects of Safety Relief Valve Hydrodynamic Loads Adequately Covered in Original Plant Design.Substantial Margins in Discharge Loads Exist)
• NLS8400179, Forwards Rev 0 to Guideline for Preparation of Emergency Operating Procedures & Procedures Generation Package, Per Suppl 1 to NUREG-0737 Requirements  + (Forwards Rev 0 to Guideline for Preparation of Emergency Operating Procedures & Procedures Generation Package, Per Suppl 1 to NUREG-0737 Requirements)
• ML20076E270  + (Forwards Rev 0 to HC.SE-PR.RL-001(Q), Hope Creek Generating Station Bailey 862 Sys Logic Module Failure Data Rept, Second Quarter 1991)
• ML18011A693  + (Forwards Rev 0 to HNP-I/INST-1045, Steam Generator Narrow Range Level:Low-Low & High-High Setpoints, for Addition to Docket 50-400)
• ML18012A770  + (Forwards Rev 0 to Harris Nuclear Plant Cycle 8 Colr. Rev Incorporates Changes Necessary as Result of Cycle 8 Core Changes & to Remove Cycle 7 Temporary Relaxation of Min Required of Detector Thimbles in Micds)
• HNP-97-101, Forwards Rev 0 to Harris Nuclear Plant Cycle 8 Colr. Rev Incorporates Changes Necessary as Result of Cycle 8 Core Changes & to Remove Cycle 7 Temporary Relaxation of Min Required of Detector Thimbles in Micds  + (Forwards Rev 0 to Harris Nuclear Plant Cycle 8 Colr. Rev Incorporates Changes Necessary as Result of Cycle 8 Core Changes & to Remove Cycle 7 Temporary Relaxation of Min Required of Detector Thimbles in Micds)
• ML20151D017  + (Forwards Rev 0 to Health Physics Monitoring Plan Green River,Ut. Comments Requested by 880502)
• ML20235M727  + (Forwards Rev 0 to Health Physics Monitoring Plan for Riverton,Wy Site)
• ML20033H058  + (Forwards Rev 0 to Health Physics Procedure RAC-024, ALARA Program & Rev 8 to RAC-002, Radiation Protection & Dosimetry Program)
• ML13324A472  + (Forwards Rev 0 to Health Physics Procedure SO1-VII-8.5.1, Process Control Program. Applicable Documents Reviewed & Approved by NRC Listed)
• L-93-019, Forwards Rev 0 to Hematite Nuclear Fuel Mfg Facility Emergency Plan & Discussion of Changes to Plan in Response to NRC Comments  + (Forwards Rev 0 to Hematite Nuclear Fuel Mfg Facility Emergency Plan & Discussion of Changes to Plan in Response to NRC Comments)
• RBG-20-164, Forwards Rev 0 to High Energy Line Break Evaluation Rept (Effect on Nonsafety-Related Control Components) in Response to Request for Addl Info 421.004 & SER Confirmatory Item 41  + (Forwards Rev 0 to High Energy Line Break Evaluation Rept (Effect on Nonsafety-Related Control Components) in Response to Request for Addl Info 421.004 & SER Confirmatory Item 41)
• ST-HL-AE-2845, Forwards Rev 0 to IE Bulletin 88-005 Investigation Rept & Suppls 1 & 2.Review Identified 158 Flanges Installed in Unit 2.No Stainless Steel Items,Nonflange Product Forms or Blind Flanges Suppliesd by Listed Companies  + (Forwards Rev 0 to IE Bulletin 88-005 Investigation Rept & Suppls 1 & 2.Review Identified 158 Flanges Installed in Unit 2.No Stainless Steel Items,Nonflange Product Forms or Blind Flanges Suppliesd by Listed Companies)
• ML20127M117  + (Forwards Rev 0 to IPE Rept for Trojan Nuclear Power Plant in Response to GL 88-20. Certifies That Individual Reviews Performed to Ensure Technical Adequacy of IPE & Validation of Results)
• ML20127M121  + (Forwards Rev 0 to IPE Rept for Trojan Nuclear Power Plant in Response to GL 88-20. Certifies That Individual Reviews Performed to Ensure Technical Adequacy of IPE & Validation of Results)

• L-94-096, Forwards Rev 0 to ISFSI Security Plan.Encl Withheld  + (Forwards Rev 0 to ISFSI Security Plan.Encl Withheld)

• BSEP-98-0087, Forwards Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports. Third 10-Yr ISI Interval Common for Bsep,Units 1 & 2  + (Forwards Rev 0 to ISI Program for Class 1,2 & 3 Components & Supports. Third 10-Yr ISI Interval Common for Bsep,Units 1 & 2)
• ML20090G159  + (Forwards Rev 0 to ISI Rept - Unit 1,McGuire 1991 Refueling Outage 7. Rept Submitted in Accordance W/Asme Code Section XI)
• ML20045C391  + (Forwards Rev 0 to ISI Rept Catawba Nuclear Station,Unit 2, Fifth Refueling Outage. Catawba,Unit 2 EOC 5 ISI Completed on 930330)
• ML15219A074  + (Forwards Rev 0 to ISI Rept Unit 2 Oconee 1993 Refueling Outage 13)
• ML20154B405  + (Forwards Rev 0 to ISI Rept for McGuire Nuclear Station Unit 1 Twelfth Refueling Outage. Relief Requests Associated with Insp Rept Which Have Been Submitted or Under Development Listed in Section 5.2)
• ML17265A226  + (Forwards Rev 0 to ISI Rept for Third Interval (1990-1999) Third Period,First Outage (1997) at Re Ginna Nuclear Power Plant.)
• ML17265A225  + (Forwards Rev 0 to ISI Rept for Third Interval (1990-1999) Third Period,First Outage (1997) at Re Ginna Nuclear Power Plant)
• ML20217E717  + (Forwards Rev 0 to ISI Rept,Unit 2 McGuire 1997 Refueling Outage 11. Rept Submitted Outside Scheduling Requirements of Article IWA-6000 of Section XI ASME Code)
• ML20117F885  + (Forwards Rev 0 to ISI Special Rept for Pressure Testing, Unit 2 Catawba 1996 Refueling Outage 7,First Ten Yr Insp Interval)
• ML20086F320  + (Forwards Rev 0 to ISI Special Rept for Pressure Testing Unit 1 Catawba 1995 Refueling Outage 8)
• ML20217J154  + (Forwards Rev 0 to ISI Summary Rept for End of Cycle 10 Refueling Outage,Per 10CFR50.4)
• ML20155A588  + (Forwards Rev 0 to ISI-22/4, Primary Reactor Containment Preoperational Integrated Leakage Rate Test, Final Rept. Test Consisted of Integrated Leakage Rate Test,Supplemental Verification Test & Bypass Test)
• ML20133F521  + (Forwards Rev 0 to ISI-3.0, Millstone Point Unit 3 Inservice Testing Program for Pumps & Valves. Requests Prompt Review & Approval in Order to Support Fuel Load Schedule of Nov 1985)
• B11744, Forwards Rev 0 to ISI-3.0, Millstone Point Unit 3 Inservice Testing Program for Pumps & Valves. Requests Prompt Review & Approval in Order to Support Fuel Load Schedule of Nov 1985  + (Forwards Rev 0 to ISI-3.0, Millstone Point Unit 3 Inservice Testing Program for Pumps & Valves. Requests Prompt Review & Approval in Order to Support Fuel Load Schedule of Nov 1985)
• PY-CEI-NRR-0614, Forwards Rev 0 to ISI-GEN-T2004, 10-Yr Inservice Insp Program Plan for Perry Nuclear Power Plant Unit 1. Plan Delineates Components Subj to Insp & Exam,W/Exception of Pump & Valve Testing,During First Insp Interval.Fee Paid  + (Forwards Rev 0 to ISI-GEN-T2004, 10-Yr Inservice Insp Program Plan for Perry Nuclear Power Plant Unit 1. Plan Delineates Components Subj to Insp & Exam,W/Exception of Pump & Valve Testing,During First Insp Interval.Fee Paid)
• ML20214P029  + (Forwards Rev 0 to ISI-P-006, Inservice Insp Program,Vogtle Electric Generating Plant,Unit 1, Per Eisenhut)
• ML20196B138  + (Forwards Rev 0 to ISI-P-014, Inservice Insp Program, for Review.Attachment a Lists Differences Between Rev 0 of Unit 2 Program & Rev 2 of Unit 1 Program)
• PLA-2705, Forwards Rev 0 to ISI-T-207.0, Component Listing & Inservice Insp 10 Yr Plan & Response to NRC 860204 Request for Addl Info on Inservice Insp Programs  + (Forwards Rev 0 to ISI-T-207.0, Component Listing & Inservice Insp 10 Yr Plan & Response to NRC 860204 Request for Addl Info on Inservice Insp Programs)
• ML17146A496  + (Forwards Rev 0 to ISI-T-207.0, Component Listing & Inservice Insp 10 Yr Plan & Response to NRC 860204 Request for Addl Info on Inservice Insp Programs)
• ML20070T351  + (Forwards Rev 0 to Il Power Co Recovery Plan,Corrective Action Program, Per Util)
• ML20074A487  + (Forwards Rev 0 to Improved Dynamic Vacuum Breaker Valve Response for Vermont Yankee, in Response to NRC 830202 Generic Ltr 83-08)
• ML20141E869  + (Forwards Rev 0 to Industrial Radiography Operating & Emergency Procedures Manual, Shipping Container QA Requirements, Per Reg Guide 7.10 Requirements.Fee Paid)
• ML20141E876  + (Forwards Rev 0 to Industrial Radiography Operating & Emergency Procedures Manual, Shipping Container QA Requirements, Per Reg Guide 7.10 Requirements.Fee Paid)
• PY-CEI-NRR-1196, Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan  + (Forwards Rev 0 to Inservice Exam Program. Program Serves as 10-yr Rev to Inservice Insp Program Plan)
• ML18018B587  + (Forwards Rev 0 to Inservice Insp Procedure ISI-201, ASME Preservice Insp Program Plan (Except Reactor Vessel), in Response to Matls Engineering Branch SER Open Item 6)