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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

• GO2-89-137, Advises That Util Review & Approval of Application for Amend to License NPF-21 Re Overcurrent Protective Relay Devices Accomplished.Fuse Size Changed from 100 to 90 Ampere to Provide Addl Margin in Containment Penetration Protection  + (ML17285A677)
• ML17285A679  + (ML17285A679)
• ML17285A681  + (ML17285A681)
• ML17285A682  + (ML17285A682)
• ML17285A683  + (ML17285A683)
• ML17285A688  + (ML17285A688)
• GO2-89-145, WPPSS-2 Semiannual Effluent Rept for Period Jan-June 1989  + (ML17285A691)
• GO2-89-143, Responds to NRC Re Violations Noted in Insp Rept 50-397/89-06.Corrective Actions:Pump Discharge Pressures Recalculated to Meet Tech Spec Requirement of 26 Psid  + (ML17285A692)
• GO2-89-138, Responds to NRC 890703 Request for Addl Info Re Use of Remaining Five Items Identified in Insp Rept 50-397/89-21. Items Include,Emd Diesel Engine Parts,Hpcs Pump Shaft,Ge Protective Relays,Chiller Shaft & Ashcroft Pressure Gauge  + (ML17285A693)
• 05000397/LER-1989-030, :on 890210,HPCS Suction Valve from Suppression Pool Failed to Fully Open During Surveillance Procedure. Caused by Motor Operator HPCS-MO-15 Mfg Design Defect.Tech Spec Action Statements Entered & Valve Closed  + (ML17285A699)
• 05000397/LER-1989-027, :on 890630,determined That Two Seismic Supports Missing on PASS Containment Isolation Valves.Caused by Inadequate Work Practices & Training of Project Personnel. Tech Spec Action Statement 3.6.1 Entered  + (ML17285A700)
• GO2-89-146, Responds to NRC Re Violations Noted in Insp Rept 50-397/89-20.Corrective Action:Memo Placed in Training Audit File Notifying Lead Auditor to Include Listed Depts in Future Audits  + (ML17285A701)
• GO2-89-147, Responds to NRC Re Violations Noted in Insp Rept 50-397/87-17.Corrective Actions:Events Analyzed & LER Submitted to Nrc,Channel Functional Test Halted & Plant Health Physics Technician Dispatched  + (ML17285A702)
• ML17285A703  + (ML17285A703)
• GO2-89-153, Application for Amend to License NPF-21,revising Tech Spec Table 3.3.1-2 to Modify Response Time Testing Required for APRM flow-biased Simulated Thermal Power Upscale Function  + (ML17285A706)
• ML17285A707  + (ML17285A707)
• ML17285A708  + (ML17285A708)
• GO2-89-152, Requests Temporary Relief from Tech Specs Surveillance Requirement Re Average Power Range Monitor Flow Biased Simulated Thermal Power Upscale Function  + (ML17285A709)
• ML17285A710  + (ML17285A710)
• 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)