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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.

List of results

• 05000397/LER-1989-032, :on 890810,discovered That non-Class 1E 120 Volt Ac Electrical Power Supply Branch Circuit Violated Electrical Separation Criteria.Caused by Equipment/Design Deficiency/Spec Less than Adequate  + (ML17285A713)
• 05000397/LER-1989-034, :on 890811,six Class 1E 480 Volt Ac Motor Control Ctrs Declared Inoperable Due to Design Deficiency. Caused by Exclusion of Fault Tripping Coordination. Distribution Sys to Be Evaluated  + (ML17285A714)
• GO2-89-151, Requests Extension to FSAR Amend 40 Submittal Date Until Sept 1989  + (ML17285A715)
• ML17285A716  + (ML17285A716)
• 05000397/LER-1989-031, :on 890806,low Reactor Pressure Vessel Level Reactor Scram Initiated by Reactor Protective Sys in Response to Actual Low Water Level Condition Caused Unplanned Trip of Reactor Feedwater Pump 1B  + (ML17285A718)
• GO2-89-156, Forwards Revised Semiannual Effluent Repts for Jan-June 1988 & Jul-Dec 1988  + (ML17285A719)
• ML17285A720  + (ML17285A720)
• ML17285A721  + (ML17285A721)
• ML17285A722  + (ML17285A722)
• GO2-89-158, Forwards Addl Info Re Underground Fire Main Analysis.Based on Results of Analyses,No Thrust Block Necessary for 12-inch Fire Main FP-43-1.ASME Rept, Flexibility Analysis of Buried Pipe, Encl  + (ML17285A723)
• ML17285A726  + (ML17285A726)
• GO2-89-159, Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S35OW Swing Check Valves or Similar Design. Results of Review Listed  + (ML17285A731)
• 05000397/LER-1989-035, :on 890817,reactor Scram Occurred During Surveillance Testing of Reactor Level Instrument Associated W/Automatic Depressurization Sys.Caused by Personnel Error. Training Improved & Visibility Increased  + (ML17285A732)
• ML17285A733  + (ML17285A733)
• GO2-89-155, Forwards Rev 9 to Washington Nuclear Plant 1 & 2 Emergency Preparedness Plan  + (ML17285A734)
• ML17285A737  + (ML17285A737)
• ML17285A738  + (ML17285A738)
• ML17285A739  + (ML17285A739)
• GO2-89-162, Forwards Proprietary MDE-88-0485, Tech Spec Improvement Analysis for Reactor Protection Sys for Washington Nuclear Project 2. Rept Withheld  + (ML17285A740)
• IR 05000397/1989020  + (ML17285A743)
• GO2-89-172, Application for Amend to License NPF-21,revising Tech Spec Sections 3.0 & 4.0 Re Recommendations of Generic Ltr 87-09  + (ML17285A744)
• ML17285A745  + (ML17285A745)
• ML17285A746  + (ML17285A746)
• PNO-V-89-058, on 890921,reactor Manually Tripped from 35% Power Due to High Conductivity in Condensate.Caused by Condenser Tube Leak,Estimated Between 5 & 10 Gpm.Licensee Estimates 8 Days for Repairs to Extraction Line & Condenser  + (ML17285A747)
• GO2-89-173, Provides Results of Testing of Sensitivity of Gamma-Metrics Monitoring Sys.Wide Range Neutron Monitoring Sys Capable of Monitoring Full Range of Sensitivity Recommended by Reg Guide 1.97,Rev 2  + (ML17285A748)

• ML17285A752  + (ML17285A752)

• 05000397/LER-1989-037, :on 890830,differential Pressure Indicating Switch RHR-DPIS-12B Discovered Isolated & Equalized.Cause Not Determined.Instrumentation & Control Work Practices Manual Developed & Training Provided  + (ML17285A753)
• ML17285A754  + (ML17285A754)
• GO2-89-175, Forwards Inservice Insp Summary Rept for Refueling Outage RF89A, for Spring 1989.Rept Includes NIS-1 Owner Data & NIS-2 Owner Repts on Repair or Replacement Completed Since Last Rept  + (ML17285A755)
• ML17285A756  + (ML17285A756)
• ML17285A757  + (ML17285A757)
• GO2-89-176, Discusses Unreviewed Safety Question Re Standby Gas Treatment,Specifically Establishing Secondary Containment Pressure within 120 of Initiation.Calculations Indicate That post-accident Doses Remain Below 10CFR100 Limits  + (ML17285A760)
• GO2-89-178, Forwards Page 2 to Inservice Insp Summary Rept Sent on 890928.During Duplication of Subj Document,Back Side of Form NIS-1 Not Copied  + (ML17285A764)
• ML17285A765  + (ML17285A765)
• 05000397/LER-1989-036, :on 890905,discovered That Present Surveillance Procedures Do Not Provide for Independent Measurement of Two Values.Caused by Less than Adequate Surveillance Procedures on Response Time Testing of APRM Sys  + (ML17285A766)
• ML17285A772  + (ML17285A772)
• ML17285A777  + (ML17285A777)
• ML17285A780  + (ML17285A780)
• ML17285A782  + (ML17285A782)
• ML17285A783  + (ML17285A783)
• GO2-89-180, Certifies That Initial & Requalification Operator Training Program for Accredited & Based on Sys Approach to Training, Per Generic Ltr 87-07  + (ML17285A784)
• ML17285A785  + (ML17285A785)
• ML17285A787  + (ML17285A787)
• ML17285A788  + (ML17285A788)
• ML17285A789  + (ML17285A789)
• 05000397/LER-1989-039, :on 890914,discovered Three Discrepancies W/ Current Configuration of Reactor Bldg Exhaust Air Radiation Monitoring Sys That Do Not Satisfy Design Basis Requirements  + (ML17285A790)
• ML17285A794  + (ML17285A794)
• ML17285A795  + (ML17285A795)
• ML17285A797  + (ML17285A797)
• IR 05000397/1989023  + (ML17285A799)
• ML17285A800  + (ML17285A800)