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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
- 1CAN039303, Application for Amend to License DPR-51,updating RCS Leakage Test Pressure in TS 4.3.2 to Agree W/Requirements of ASME Boiler & Pressure Vessel Code,Section XI (Through Winter 1981 Addenda) + (ML20035A728)
- ML20035A731 + (ML20035A731)
- ML20035A732 + (ML20035A732)
- 0CAN039308, Submits Request for Extension to Complete Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Recommendations + (ML20035A733)
- ML20035A734 + (ML20035A734)
- ML20035A735 + (ML20035A735)
- ML20035A736 + (ML20035A736)
- LIC-93-0097, Forwards Decommissioning Cost Study for Fort Calhoun Station Unit 1, Rev 1 + (ML20035A738)
- ML20035A741 + (ML20035A741)
- ML20035A744 + (ML20035A744)
- ML20035A745 + (ML20035A745)
- ML20035A746 + (ML20035A746)
- JPN-93-021, Forwards Inservice Insp Summary Rept,1992 Refuel Outage (Reload 10/Cycle 11), Consisting of Results of Jet Pump Beam Insps Performed Per NRC Bulletin 80-07 & Access Hole Cover Insps Performed Per GE SIL 462 + (ML20035A747)
- ML20035A749 + (ML20035A749)
- ML20035A751 + (ML20035A751)
- ML20035A752 + (ML20035A752)
- B14360, Application for Amend to License DPR-61,revising TS 3.8.3.2.b to Allow Use of Tie Breakers 6T11 & 11T6 to Facilitate Energizing Bus 11 & Bases Section 3/4.4.4 to Address Failure of Pressurizer Pressure Channel + (ML20035A753)
- BSEP-93-0041, Part 21 Rept Re Mfg Defects Associated W/Westinghouse Type Hmcp & Type Hfd Breakers,Resulting in Possibility That Breaker Contacts May Not Open During Trip.Initially Reported on 930225.Functional Testing Procedures Revised + (ML20035A755)
- ML20035A756 + (ML20035A756)
- ML20035A757 + (ML20035A757)
- LIC-93-0098, 1992 OPPD Annual Rept + (ML20035A758)
- ML20035A759 + (ML20035A759)
- B14403, Application for Amend to License DPR-21,revising TS LCO 3.6B,SR 4.6.B,Figures 3.6.1,3.6.2 & 3.6.3 Along W/Bases for Section 3.6 W/Respect to pressure-temp Limit Curves.Rev 1 to GE-NE-523-165-1292 Encl + (ML20035A761)
- ML20035A764 + (ML20035A764)
- ML20035A765 + (ML20035A765)
- ML20035A766 + (ML20035A766)
- ML20035A768 + (ML20035A768)
- 05000370/LER-1993-001-02, :on 930222,discovered That SG C Feedwater Flow Low & Decreasing Even Though Controller Output Increasing, Resulting in Manual Reactor Trip.Caused by Equipment Failure.All Pneumatic Relays Replaced + (ML20035A770)
- 1CAN039306, Forwards Response to NRC 921116 Request for Addl Info Re in- Structure Response Spectra in Order to Complete Review of 920918 Response to Suppl 1 to GL 87-02 on Rev 2 to SQUG Generic Implementation Procedure + (ML20035A771)
- LD-93-052, Forwards Minor Revs to Draft SER Responses Requested by NRC Reviewer on Sys 80+ QA Program,Including Rev of Table 3.2-1 to Show Graded Quality Classifications for Sys 80+ Structures,Sys & Components + (ML20035A772)
- LD-93-053, Forwards Design Description & ITAAC for Sys 80+ Nuclear Island Structure.Encl Info Should Be Incorporated in Review of Prototype Sys 80+ Design Description & ITAAC Expected on 930329-0401 + (ML20035A773)
- ML20035A774 + (ML20035A774)
- 1CAN039302, Application for Amend to License DPR-51,revising TS Table 4.18-2 & Spec 4.18.6 Re C-3 Repts to Be Consistent W/B&W STS + (ML20035A776)
- ML20035A778 + (ML20035A778)
- 05000373/LER-1993-009, :on 930302,discovered Three Open Corebore Penetrations in Floor of 3 H Fire Rated Assembly.Cause of Event Unknown.Hourly Fire Watch Established & Work Request Written to Have Corebores Filled W/Grout + (ML20035A779)
- ML20035A780 + (ML20035A780)
- ML20035A782 + (ML20035A782)
- ML20035A783 + (ML20035A783)
- ML20035A785 + (ML20035A785)
- ML20035A786 + (ML20035A786)
- ML20035A787 + (ML20035A787)
- B14412, Responds to NRC Re Violations Noted in Insp Repts 50-245/92-29,50-336/92-31 & 50-423/92-28 on 921028-1222. C/As:Plant Design Change Records Will Be Revised to Include Requirements for Timely Pdcr Closeouts & FSAR Changes + (ML20035A789)
- B14314, Forwards Updated Rept on Haddam Neck Plant Integrated Safety Assessment Program (Isap) Re License Condition Issued by NRC in License Amend 150 + (ML20035A790)
- ML20035A791 + (ML20035A791)
- B14407, Reactor Containment Bldg ILRT Rept + (ML20035A793)
- ML20035A794 + (ML20035A794)
- ML20035A795 + (ML20035A795)
- ML20035A796 + (ML20035A796)
- NRC-93-0041, Forwards Rev 21 to Fermi 2 Physical Security Plan Per 10CFR50.54(p)(2).Plan Withheld + (ML20035A798)
- ML20035A800 + (ML20035A800)
- ML20035A801 + (ML20035A801)