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A list of all pages that have property "Title" with value "Forwards Reactor Containment Bldg Structural Acceptance Test.". Since there have been only a few results, also nearby values are displayed.

Showing below up to 26 results starting with #1.

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List of results

  • ML20055J163  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Quad-Cities Nuclear Power Station Unit 2,900427-28, & Related Apps Describing Type a Test,Per 10CFR50,App J, Section V.B.1.Next Test Scheduled for Fall 1991)
  • ML20053B874  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Types A,B & C,Surveillance Test)
  • ML20106E188  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Types A,B & C Periodic Test, for Units 1 & 2,per 10CFR50,App J)
  • ML18096A797  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test, Performed During Unit 2 Sixth Refueling Outage from 920322-24)
  • ML18096A798  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test, Performed During Unit 2 Sixth Refueling Outage from 920322-24)
  • ML13317B187  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test, Final Rept.Measured Leak Rate Test & Supplemental Verification Test Met Acceptance Criteria in Tech Specs)
  • ML18009A353  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence)
  • ML18009A355  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Conducted in Oct 1989.Util Believes That Packing Leaks Discovered Are Isolated Failures & That Repair Should Prevent Recurrence)
  • ML17348B358  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test (ILRT) - 1991 Turkey Point,Unit 4,ILRT - Date of Test Completion:911020)
  • ML20024H622  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test (910202-0305) Braidwood Unit 1)
  • ML18149A410  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test,Type A,B & C Periodic Tests, Per 10CFR50,App J)
  • ML18149A411  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test,Type A,B & C Periodic Tests, Per 10CFR50,App J)
  • ML20237C786  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test & Separate Accompanying Summary Rept of Type B & C Results)
  • L-82-281, Forwards Reactor Containment Bldg Integrated Leak Rate Test,Types A,B & C  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test,Types A,B & C)
  • PM-78-411, Forwards Reactor Containment Bldg Integrated Leak Rate Test for Subj Facil  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test for Subj Facil)
  • ML20101K325  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test,Sept 1984. Results of Leak Rate Test Performed Discussed)
  • JAFP-90-0742, Forwards Reactor Containment Bldg Integrated Leakage Rate Test, & Containment Isolation Valve Replacement Program Rept  + (Forwards Reactor Containment Bldg Integrated Leakage Rate Test, & Containment Isolation Valve Replacement Program Rept)
  • PM-78-507, Forwards Reactor Containment Bldg Integrated Leakage Rate Test Final Rept,  + (Forwards Reactor Containment Bldg Integrated Leakage Rate Test Final Rept,)
  • ML18139A489  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test,Types A,B & C,Surveillance Test.)
  • L-83-435, Forwards Reactor Containment Bldg Integrated Leak Rate Test Type A,B & C Periodic Test,Florida Power & Light Co,Turkey Point Plant,Unit 4  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Type A,B & C Periodic Test,Florida Power & Light Co,Turkey Point Plant,Unit 4)
  • ML20197A755  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test,Quad-Cities Nuclear Power Station,Unit 1,860322-23. Next Type a Test Scheduled for Fall 1987)
  • ML20069D953  + (Forwards Reactor Containment Bldg Integrated Leak Rate Test Type A,B & C Preoperational Test)
  • ML18092A368  + (Forwards Reactor Containment Bldg Second Inservice Integrated Leak Rate Test & Types B & C Surveillance Test. Testing Conducted Under Differential Preoperational Test Condition,In That Some Monitor Channels Plugged Shut)
  • ML18092A369  + (Forwards Reactor Containment Bldg Second Inservice Integrated Leak Rate Test & Types B & C Surveillance Test. Testing Conducted Under Differential Preoperational Test Condition,In That Some Monitor Channels Plugged Shut)
  • ML20003D500  + (Forwards Reactor Containment Bldg Structural Acceptance Test)
  • ML20003D501  + (Forwards Reactor Containment Bldg Structural Acceptance Test.)
  • ML18093A763  + (Forwards Reactor Containment Bldg Third/Final Inservice Integrated Leak Rate Test,First 10-Yr Insp Interval & Type B & C Surveillance Tests, Per 10CFR50,App J,Section V.B)
  • ML18093A765  + (Forwards Reactor Containment Bldg Third/Final Inservice Integrated Leak Rate Test,First 10-Yr Insp Interval & Type B & C Surveillance Tests, Per 10CFR50,App J,Section V.B)
  • TXX-3664, Forwards Reactor Containment Bldg Unit 1 Preoperational Integrated Leak Rate Test,1983. Electrical Penetrations Leaked Excessively During Testing.Further Testing to Determine Cause of Leakage in Progress  + (Forwards Reactor Containment Bldg Unit 1 Preoperational Integrated Leak Rate Test,1983. Electrical Penetrations Leaked Excessively During Testing.Further Testing to Determine Cause of Leakage in Progress)
  • ML19210A108  + (Forwards Reactor Containment Bldg:Integrated Leak Rate Test,Apr 1978)
  • ML19210A109  + (Forwards Reactor Containment Bldg:Integrated Leak Rate Test,Apr 1978.)
  • ML19210A337  + (Forwards Reactor Containment Bldg:Ring Girder Surveillance Two Yrs After Structural Integrity Test. W/O Encl)
  • ML19210A554  + (Forwards Reactor Containment Bldg:Second Tendon Surveillance Test Three Yrs After Structural Integrity Test. W/O Encl)
  • LIC-94-0037, Forwards Reactor Containment Building Integrated Leakage Rate Test Rept,Nov 1993,Sixth Periodic Test for Fort Calhoun Station Unit 1  + (Forwards Reactor Containment Building Integrated Leakage Rate Test Rept,Nov 1993,Sixth Periodic Test for Fort Calhoun Station Unit 1)
  • ML20126C822  + (Forwards Reactor Containment Building Integrated Leakage Rate Test for Comanche Peak Steam Electric Station Unit 2 Final Rept, Reflecting Summary of Unit 2 Prestart Test Program ILRT Conducted During Period 920910-15)
  • ML20072E505  + (Forwards Reactor Containment ILRT Comm Ed Braidwood Nuclear Power Station Unit 1 Conducted from 940304-0422.Rept Describes Second Unit 1 Type a Containment Leakage Rate Test Performed Using Technical Surveillance 1BwVS 6.1.2.a-1)
  • ML20063A044  + (Forwards Reactor Containment Integrated Leakage Rate Test Results Rept 1982, Summarizing Performance of Type a & 1980 & 1982 Type B & Type C Local Leak Rate Test Results)
  • ML18082A121  + (Forwards Reactor Containment Integrated Leak Rate Test, First Retest - Aug 1979.)
  • ML18082A120  + (Forwards Reactor Containment Integrated Leak Rate Test, First Retest - Aug 1979)
  • ML20070T031  + (Forwards Reactor Coolant & Main Steam Line Tunnel Leakage Detection Sys Performance Evaluations After 5 Yrs of Operation.Performance History of Both Sys Excellent)
  • ML17336A022  + (Forwards Reactor Coolant Processing Plan, Which Serves as App 1 to Submerged Demineralizer Sys Technical Evaluation Rept)
  • 1CAN119603, Forwards Reactor Coolant Pump Flywheels Inservice Insp Results Which Suppl Table 3-1 of Rept Included W/Initial TS Change Request  + (Forwards Reactor Coolant Pump Flywheels Inservice Insp Results Which Suppl Table 3-1 of Rept Included W/Initial TS Change Request)
  • ML13310A807  + (Forwards Reactor Coolant Pump Rotor Seizure/Shaft Break Accident Analysis, in Response to 820210 Request for Addl Info Re SEP Topic XV-7.Environ Consequence Analysis Unnecessary)
  • ML18139A422  + (Forwards Reactor Coolant Pump Support Drawings & Description of Pump Support Disassembly & Insp Procedures,In Response to NRC)
  • ML18130A316  + (Forwards Reactor Coolant Pump Support Drawings & Description of Pump Support Disassembly & Insp Procedures,In Response to NRC 800707 Ltr)
  • ML13317B063  + (Forwards Reactor Coolant Subcooling Monitoring Sys Error Analysis Per 800213 & 0411 Ltrs.Info Reflects Sys Upgrade & Provides Basis for Accuracy of Sys)
  • ML19224C116  + (Forwards Reactor Core Letdown Analysis of Pressurized Sample Taken on 790502)
  • ML20097J512  + (Forwards Reactor Decommissioning Rept & Final Status Surveys in Accordance W/Approved Decommissioning Plan.All Survey Data Confirms That Facility Meets Release Criteria for Unrestricted Use Established in Decommissioning Plan)
  • ML20039A597  + (Forwards Reactor Emergency Cooling Analysis 3 Code Verification W/Region Constraint Devices Installed, Per Amend 22 to OL)
  • ML20213E413  + (Forwards Reactor Fuel Section Input to Supplemental SER Re Waterside Corrosion & Fuel Rod Bowing.Issues Resolved)
  • ML19220C275  + (Forwards Reactor Fuels Section & Physics Section Input to Ser.W/O Encl)
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