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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
- TXX-6587, Interim Deficiency Rept CP-87-24 Re Engineering Approval Allowing Bending of Nelson Stud Anchors on Containment Liners in Excess of FSAR Requirements.Initially Reported on 870629.Evaluation Continuing.Next Rept Expected by 870828 + (ML20236E566)
- ML20236E568 + (ML20236E568)
- GO2-89-108, Forwards Rev 14 to Plant Physical Security Plan.Rev Withheld (Ref 10CFR73.21) + (ML20236E570)
- ML20236E573 + (ML20236E573)
- ML20236E574 + (ML20236E574)
- ML20236E575 + (ML20236E575)
- 05000424/LER-1987-042, :on 870626,discovered That Boron Concentration Exceeds Tech Spec Limiting Condition of Operation Time Limit.Caused by Chemistry Technician Inattention to Detail. Personnel Involved Counseled & Memo Issued + (ML20236E576)
- IR 05000413/1987034 + (ML20236E577)
- ML20236E579 + (ML20236E579)
- ML20236E580 + (ML20236E580)
- ML20236E581 + (ML20236E581)
- ML20236E582 + (ML20236E582)
- ST-HL-AE-1000, Forwards Corrected Pages 3-1,6-1,7-1 & A-1 to Rev 12 of Security Personnel Training & Qualification Plan.Corrections Have No Impact on Intent of Rev 12 Submittal,Other than Clarification.Corrected Pages Withheld + (ML20236E584)
- ML20236E586 + (ML20236E586)
- ML20236E588 + (ML20236E588)
- NUREG/CR-4981, Forwards Fr Notice on Denial of Committee to Bridge Gap Petition for Rulemaking Re Fire Response Plans for Graphite Fires & BNL Rept,NUREG/CR-4981 Re Safety Assessment of Use of Graphite in Nuclear Reactors Licensed by NRC + (ML20236E589)
- ML20236E590 + (ML20236E590)
- ML20236E592 + (ML20236E592)
- 05000395/LER-1989-011, :on 890528,manual Reactor Trip Initiated Following Pressurizer Safety Value Failure.Cause Under Investigation.Operators Monitored RCS Pressure & Prepared to Initiate Safety Injection + (ML20236E593)
- ML20236E594 + (ML20236E594)
- ML20236E595 + (ML20236E595)
- ML20236E596 + (ML20236E596)
- ML20236E597 + (ML20236E597)
- NRC-89-0104, Comment Supporting Proposed Rule 10CFR50, Acceptance of Products Purchased for Use in Nuclear Power Plant Structures,Sys & Components + (ML20236E598)
- DD-87-10, Informs That Time within Which Commission May Act to Review Directors Decision DD-87-10 Expired.Commission Declined Review.Decision Became Final Agency Action on 870720.Served on 870728 + (ML20236E599)
- ML20236E600 + (ML20236E600)
- ML20236E601 + (ML20236E601)
- IR 05000219/1987021 + (ML20236E602)
- ML20236E603 + (ML20236E603)
- ML20236E604 + (ML20236E604)
- ML20236E605 + (ML20236E605)
- ML20236E606 + (ML20236E606)
- IR 05000324/1976008 + (ML20236E608)
- ML20236E610 + (ML20236E610)
- ML20236E611 + (ML20236E611)
- PNO-IV-87-035, licensee Initiated Plant Shutdown,Estimated to Last Approx 35 Days,To Replace Helium Coolant Circulation 1D.Circulation Developed Wobble & Penetration Interspace Seal Leak of Purified Helium.State of Co Will Be Informed + (ML20236E612)
- ML20236E613 + (ML20236E613)
- ML20236E615 + (ML20236E615)
- ML20236E616 + (ML20236E616)
- ML20236E617 + (ML20236E617)
- ML20236E618 + (ML20236E618)
- ML20236E619 + (ML20236E619)
- NUREG/CR-5088, Discusses Proposed Actions Re SECY-89-170, Fire Risk Scoping Study:Summary of Results & Proposed Staff Actions, (NUREG/CR-5088).Need for Addl Research Will Be Considered Following Final Definition of fire-related Parts + (ML20236E620)
- ML20236E621 + (ML20236E621)
- ML20236E624 + (ML20236E624)
- ML20236E626 + (ML20236E626)
- ML20236E627 + (ML20236E627)
- ML20236E629 + (ML20236E629)
- ML20236E631 + (ML20236E631)
- ML20236E632 + (ML20236E632)
- ML20236E635 + (ML20236E635)