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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
- ML20077D434 + (ML20077D434)
- ML20077D438 + (ML20077D438)
- ML20077D439 + (ML20077D439)
- ML20077D441 + (ML20077D441)
- ML20077D444 + (ML20077D444)
- ML20077D446 + (ML20077D446)
- ML20077D448 + (ML20077D448)
- ML20077D449 + (ML20077D449)
- ML20077D453 + (ML20077D453)
- ML20077D454 + (ML20077D454)
- ML20077D457 + (ML20077D457)
- ML20077D461 + (ML20077D461)
- ML20077D465 + (ML20077D465)
- ML20077D470 + (ML20077D470)
- ML20077D471 + (ML20077D471)
- ML20077D472 + (ML20077D472)
- ML20077D475 + (ML20077D475)
- ML20077D493 + (ML20077D493)
- ML20077D496 + (ML20077D496)
- ML20077D502 + (ML20077D502)
- ML20077D511 + (ML20077D511)
- 2CAN068313, Identifies Precautionary Measures to Be Taken Re Shape Annealing Matrix (SAM) Transposition,Inadvertently Omitted from .Procedure Mods Planned to Ensure SAM Valves Properly Calculated + (ML20077D524)
- ML20077D527 + (ML20077D527)
- TXX-4011, Forwards Affidavit of Svc Re Amend 41 to FSAR + (ML20077D529)
- ML20077D535 + (ML20077D535)
- 05000296/LER-1983-035-03, /03L-0:on 830620,while Performing Primary Containment Isolation Valve Operability Test,Valve FCV-69-2 Would Not Fully Close.Caused by Valve Operator Motor Breaker Tripping Due to Armature Winding Failure + (ML20077D537)
- 05000368/LER-1983-026-03, /03L-0:on 830620,deficient Fire Barrier Penetration Seals Discovered Between Walls Providing Access to Electrical Equipment & Cable Spreading Rooms.Cause Not Stated.Fire Watch Posted.Seals Repaired + (ML20077D539)
- ML20077D540 + (ML20077D540)
- ML20077D541 + (ML20077D541)
- 05000395/LER-1983-067-03, /03L-0:from 830601 to 19,reactor Bldg Sump Inventory Not Performed,Contrary to Tech Spec Surveillance Requirement 4.4.6.2.1.b.Caused by Personnel Failure to Implement Alternative Inventory Method + (ML20077D543)
- 05000369/LER-1983-043, Forwards LER 83-043/01T-0 & 83-029/01T-0 + (ML20077D546)
- ML20077D549 + (ML20077D549)
- W3P83-1220, Requests That Supplemental SER Be Written to Remove License Condition Re LER on MW Demand Setter or Reactor Power Cutback Malfunctions.Procedure UNT-6-002 Revised to Require LER on Noted Malfunctions + (ML20077D550)
- W3P83-1227, Requests That Supplemental SER Be Written to Removal License Condition Re Reevaluation of Essential Vs Nonessential Sys, Per Rev 2 to Reg Guide 1.141.Review Should Commence When Reg Guide Issued + (ML20077D552)
- 05000260/LER-1983-035-03, /03L-0:on 830621,during Local Power Range Monitor Calibr,Calculated R Factor,Maplhgr & Linear Heat Generation Rate Limits Exceeded.Caused by Uncalibr Range Monitor Distribution Due to Set Up of New Rod Pattern + (ML20077D557)
- ML20077D558 + (ML20077D558)
- 05000369/LER-1983-043-01, /01T-0:on 830601,Westinghouse Notified Util That Extended Operation at Lower Power & Subsequent Escalation to Power in Same Fuel Cycle Would Result in Heat Flux Hot Channel Factor Limit Violations to LOCA Analysis + (ML20077D559)
- W3P83-1225, Requests That SER Suppl Be Written to Delete License Condition Re ECCS Preoperational Testing + (ML20077D564)
- ML20077D566 + (ML20077D566)
- 05000369/LER-1983-029-01, /01T-0:on 830601,Westinghouse Notified Util That Extended Operation at Low Power & Subsequent Escalation to Power in Same Fuel Cycle Would Result in Heat Flux Hot Channel Factor Limit Violations for LOCA Analysis + (ML20077D567)
- ML20077D570 + (ML20077D570)
- ML20077D573 + (ML20077D573)
- ML20077D581 + (ML20077D581)
- ML20077D598 + (ML20077D598)
- NRC-94-4352, Forwards Proprietary LOFTRAN-AP Core Makeup Tank Preliminary Validation Rept, MT01-GSR-002.Rept Withheld Per 10CFR2.790.Proprietary Portion of Document Sent to Westinghouse + (ML20077D646)
- A09351, Responds to NRC Ltr Re Violations Noted in Allegation RI-90-A-232.After Review & Evaluation,Licensee Finds That None of Issues Taken Either Singularly or Collectively Present Any Indication of Compromise of Nuclear Safety + (ML20077D654)
- A09353, Responds to NRC Ltr Re Violations Noted in Allegation RI-90-A-106.After Review & Evaluation,Licensee Finds That None of Issues Taken Either Singularly or Collectively Present Any Indication of Compromise of Nuclear Safety + (ML20077D658)
- ML20077D659 + (ML20077D659)
- A09352, Responds to NRC Ltr Re Violations Noted in Allegation RI-90-A-221.After Review & Evaluation,Licensee Finds That Issues Taken Either Singularly or Collectively Do Not Present Any Indication of Compromise of Nuclear Safety + (ML20077D661)
- ML20077D666 + (ML20077D666)
- A09354, Responds to NRC Ltr Re Violations Noted in Allegation RI-90-A-187.After Review & Evaluation,Licensee Finds That No Issues Taken Either Singularly or Collectively Present Any Indication of Compromise of Nuclear Safety + (ML20077D671)