Search by property

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

• ML20079L231  + (ML20079L231)
• ML20079L233  + (ML20079L233)
• ML20079L235  + (ML20079L235)
• PY-CEI-NRR-1390, Proposed Tech Specs Table 3.3.2-2, Reactor Water Cleanup Sys Isolation Actuation Instrumentation  + (ML20079L250)
• 05000280/LER-1982-129, Forwards LER 82-129/03L-0  + (ML20079L253)
• ML20079L256  + (ML20079L256)
• ML20079L261  + (ML20079L261)
• ML20079L262  + (ML20079L262)
• ML20079L264  + (ML20079L264)
• ML20079L266  + (ML20079L266)
• ML20079L267  + (ML20079L267)
• ML20079L268  + (ML20079L268)
• 05000280/LER-1982-129-03, /03L-0:on 821202,performance of Periodic Test 27 Revealed Amp Reading for Panel 1,circuit 23A Not within Acceptance Criteria.Caused by Faulty Thermostat.Thermostat Replaced  + (ML20079L269)
• ML20079L270  + (ML20079L270)
• ML20079L271  + (ML20079L271)
• 2CAN109108, Submits Schedule for Completion of Generic Bounding Analysis of Surge Line Thermal Stratification,Per NRC Bulletin 88-011.Surge Line Design Documentation Will Be Updated by 920630 or within 3 Months of Favorable NRC SER  + (ML20079L272)
• ML20079L273  + (ML20079L273)
• PY-CEI-NRR-1389, Proposed Tech Specs Tables 3.3.2-1 Re Isolation Actuation Instrumentation & 3.3.3-1 Re ECCS Actuation Instrumentation  + (ML20079L275)
• RBG-14-393, Interim Deficiency Rept DR-23 Re HPCS Diesel Generator Radiant Heat Loss Value Used in Sizing of HPCS Room Cooling Design.Initially Reported on 820212.Util Awaiting Addl Info from GE to Complete Evaluation.Final Rept by 830429  + (ML20079L281)
• ML20079L283  + (ML20079L283)
• ML20079L290  + (ML20079L290)
• ML20079L293  + (ML20079L293)
• 05000321/LER-1983-010, Forwards LER 83-010/03L-0  + (ML20079L295)
• ML20079L297  + (ML20079L297)
• ML20079L303  + (ML20079L303)

• 05000321/LER-1983-010-03, /03L-0:on 830110,during Reactor Coolant Instrumentation Lines Excess Flow Check Valve Operability review,12 Valves Found Inoperable.Caused by Electrical & Mechanical Component Failures.Valves Repaired/Replaced  + (ML20079L305)

• DCL-91-261, Forwards Implementation Plan for Operation of Emergency Response Data Sys,Per Generic Ltr 89-15.Formal Testing of Sys W/Nrc Will Be Conducted in June 1992 & Sys Will Be Brought on-line by Dec 1992  + (ML20079L308)
• 05000327/LER-1983-010, Forwards LER 83-010/03L-0  + (ML20079L310)
• ML20079L311  + (ML20079L311)
• ML20079L312  + (ML20079L312)
• 05000366/LER-1980-049, Forwards Updated LER 80-049/03X-1  + (ML20079L318)
• ML20079L319  + (ML20079L319)
• ML20079L323  + (ML20079L323)
• PY-CEI-NRR-1408, Responds to NRC Re Violations Noted in Insp Rept 50-440/91-15 on 910819-23 & 0919.Corrective Actions: Surveillance Instruction (SVI-G50-T8004) Modified & Perry Worker Practices Training Course Will Be Modified  + (ML20079L324)
• 05000327/LER-1983-010-03, /03L-0:on 830118,during Performance of Surveillance Instruction 7,diesel Generator 1A-A Tripped on High Water Jacket Temp.Caused by ERCW Valve 1-FCV-67-66 Failing to Open.No Cause Found  + (ML20079L331)
• ML20079L335  + (ML20079L335)
• 2CAN109111, Advises That on 911009,Amend 123 to License NPF-6 Became Effective.Amend Requires That Special Rept Be Submitted within 30 Days Following Failure.Probe Discovered Failed on 901221 Will Be Replaced During Next Refueling Outage  + (ML20079L336)
• ML20079L343  + (ML20079L343)
• ML20079L344  + (ML20079L344)
• AECM-83-0093, Monthly Operating Rept for Jan 1983  + (ML20079L346)
• ML20079L347  + (ML20079L347)
• 05000397/LER-1983-001-03, /03L-0:on 831225,while Loading First Fuel Bundle, Rod Block Protective Interlock Lost.Caused by Misinterpretation of Tech Spec Intent.Calibr & Survillance Procedures Changed  + (ML20079L348)
• 05000361/LER-1983-154-03, /03L-0:on 831211,during Mode 5 Outage,Channel a Pressurizer Level Transmitter 2LT-0110-1 Found Inoperable During Performance of 18-month Calibr.Caused by Empty Ref Leg.Leg Filled  + (ML20079L350)
• 05000259/LER-1983-073-01, /01T-0:on 831231,reactor Coolant Sample Indicated Chloride Concentration of 525 Ppb & Conductivity & Offgas Radiation Level Increased While Ph Decreased.Caused by Resin Intrusion Into Reactor Vessel.Trap Replaced  + (ML20079L353)
• ML20079L355  + (ML20079L355)
• ML20079L361  + (ML20079L361)
• 05000366/LER-1980-049-03, While Performing Standby Liquid Control Pump Operability & Relief Valve Test,Sblc Pump B Discharge Relief Valve Failed to Operate at Required Pressure.Caused by Setpoint Drift  + (ML20079L362)
• 05000395/LER-1983-076-03, Pressurizer PORV PCV-444B-RC Would Not Fully Stroke When Operated from Main Control Board.Caused by Low Operating Pressure.Regulator for PCV-44B-RC Replaced  + (ML20079L363)
• 05000373/LER-1991-011-05, :on 911002,TS Surveillance Missed During Primary Containment Due to Missed Prerequisite C.6 in Procedure LOP-VQ-11.Procedure LOP-VQ-11 Will Be Revised & Operating Dept Will Be Trained on Event  + (ML20079L369)
• JPN-91-060, Forwards Response to Generic Ltr 91-06, Resolution of Generic Issue A-30, Adequacy of Safety-Related DC Power Supplies. Advises That Design,Maint,Surveillance & Test Procedures for Dc Power Supplies Reasonable Alternatives  + (ML20079L370)
• ML20079L372  + (ML20079L372)