Conval
Conval# QUERYed671a853feb32fdb5c20895b2641936
JAFP-92-0470, Ja Fitzpatrick Nuclear Power Plant Annual Summary of Changes,Tests & Experiments for 1990
JAFP-86-0770, Annual Summary of Changes,Tests & Experiments for 1985
BECO-89-109, Forwards Summary of Changes,Tests & Experiments for 880122-890121
B13224, Forwards Request for Schedular Exemption from Requirements of 10CFR50,App J,Sections III.A.6.(b),III.D.2(a) & III.D.3. Exemptions Will Provide Relief from Requirements for Penalty Type a Test Intervals During 1989 Refueling Outage
BVY 13-061, VY-RPT-12-00019, Revision 1, Vermont Yankee Seismic Walkdown Submittal Report for Resolution of Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page 159 of 505 of Attachment C
L-13-027, Sixteenth Refueling Outage Inservice Inspection Summary Report
05000271/LER-1986-016, :on 861110,discovered App J Leak Test Not Performed as Required by Tech Specs.Caused by Personnel Error.Valve RWCU-68 Successfully Leak Tested.Personnel Counseled
JAFP-97-0202, Annual Summary of Plant Changes,Tests & Experiments for 1996
JPN-91-039, Responds to Request for Addl Info Re Generic Ltr 89-10, Suppl 3, Consideration of Results of NRC-Sponsored Tests of Motor-Operated Valves, Per
JAFP-88-0687, Forwards Lists of suppliers,sub-tier Suppliers & Mfgs from Which safety/nonsafety-related Fasteners Purchased in Compliance with NRC Compliance Bulletin 87-002
05000315/LER-1986-011-01, :on 860528,lower Containment Airborne Particulate Monitors Train a & B High Alarmed.Caused by Leaking Valves Mfg by Velan,Copes-Vulcan,Inc & Conval,Inc. Valves Repaired
BSEP-92-0050, Annual Rept Per 10CFR50.59 for 1991. Rept Contains Tests & Experiments Conducted in 1991 But Not Described in Fsar
JAFP-88-0099, Responds to NRC Compliance Bulletin 87-002.All safety- Related & Nine non-safety Related Fasteners within Required Specs.Specs for Three non-safety Related Fasteners Not Met, Listed.Supporting Info Encl
L-14-243, Seventeenth Refueling Outage Inservice Inspection Summary Report
BSEP-91-0162, Responds to Violations Noted in Insp Repts 50-324/91-02 & 50-325/91-02.Corrective actions:O-rings Will Be Replaced & Valves Cleaned on Unit 2 Valves W/Incorrect Lubricant Applied & Direct Replacement Valves Will Be Retested
LIC-14-0039, Refueling Outage Inservice Inspection Results
JAFP-88-0047, Provides Response to Action Item F of IE Bulletin 85-003. Valves within Scope of Bulletin Would Have Performed Safety Functions W/Two Exceptions,Per Results of as-found Testing. Supporting Documentation Encl
05000298/LER-1985-005, :on 850818,discovered Two Type B & Nine Type C Penetration Failures During Primary Containment Local Leak Rate Testing,Resulting in Excessive Leak Rate.Cause Not Stated.Valves Replaced or Repaired
RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5
05000316/LER-1985-007, :on 841228,NDE Revealed Cracks in Seven 2-inch Rockwell-Edward Globe Valves,Similar to IE Info Notice 84-48 & Suppl 1 Description.Valves Isolate Reactor Coolant Loop Resistance Temp Detector Manifolds
05000271/LER-1992-010, :on 920308,12 & 17,liquid Radwaste Valve, Feedwater Check Valve & CRD Valves Found W/Seat Leakage Above Ts.Caused by Equipment Wear/Age & Mfg Defect.Valves Repaired,Replaced or Successfully Retested
05000293/LER-1995-006, :on 950614,RCIC Sys Made Inoperable for Troubleshooting Problem W/Turbine Steam Supply Valve.Caused by Either Loosened wire-connector or Failed Auxiliary seal- in Relay.Relay Replaced & Wires Checked
05000298/LER-1983-013-03, /03L-0:on 830831,during Local Leak Rate Test, Procedure 6.3.1.1,20,penetrations Found Leaking Excessively. Caused by Discs & Seats Being Lapped.Valves Repaired
05000298/LER-1983-013, Forwards LER 83-013/03L-0.Detailed Event Analysis Encl
BSEP-93-0232, 1992 Annual Rept in Accordance W/10CFR50.59
05000293/LER-1993-018, :on 930721,planned Shutdown Initiated Due to Unidentified Leakage of 3 Gpm.On 930722,planned Shutdown Became TS Required Shutdown When Insp Revealed Leakage to Be Rc Pressure Boundary Leakage.Leakage Repaired
05000315/LER-1982-023-03, /03L-0:on 820416,west motor-driven Auxiliary Feed Pump Removed from Svc to Repair Emergency Leakoff Line Check Valve FW-160.Check Valve Not Seated Tightly.Seat Lapped & Plug Conval Part 5F-316 Replaced.Mod Initiated
05000293/LER-1993-002, :on 930225,RCIC Sys Declared Inoperable During Surveillance Testing.Caused by Galling of Valves Stem & Bonnet Chamber.Valve Stem & Bonnet Chamber Will Be Replaced & Parts Will Be Purchased Following Design
05000247/LER-1983-018-03, /03L-0:on 830422,plant Shutdown Commenced When Binding of Valve 1870 Could Not Be Corrected within Tech Spec Time Period.Cause Not Stated.Binding Alleviated by Lubricating Valve Stem & Universal Joints
05000247/LER-1983-019-03, /03L-0:on 830422,valve 743,nonautomatic Containment Isolation Valves in RHR Pump Miniflow Line Would Not Operate.Cause Not Stated.Reach Rods Disconnected & Valve Stem & Universal Joints Cleaned & Lubricated
05000315/LER-1995-006, :on 950825,containment Type B & C Exceeded LCO Value Due to Leakage of Post Accident Sample Line Check Valve & Ice Condenser Glycol Header Isolation Valve Pressure Relief Check Valve.Evaluated Event
05000315/LER-1992-007, :on 920705,accumulated Leakage for Type B & C Leakrate Tests on Containment Penetrations Exceeded TS Lco. Caused by Scale on Valve Seat & Small Crack in Surface of Neoprene Seat.Stop Nuts Adjusted
05000315/LER-1990-015, :on 901102,discovered Containment Type B & C Leakage Exceeded L.C.O. Value Due to Degradation of Isolation Valve Seating Surfaces.Seat Was Lapped & Disc Was Replaced
05000315/LER-1989-009, :on 890705,disovered That Testing Document for Valve 1-CS-443-2 Not Signed Off.Record Search Conducted & No Evidence Found to Indicate That post-maint Testing Performed.Caused by Personnel Error
AEP-NRC-2014-50, Response to Regulatory Issue Summary 2014-07 Enhancements to the Vendor Inspection Program - Vendor Information Request
NL-09-119, Proposed License Amendment Regarding Diesel Generator Air Start Receiver Pressure, Indian Point Units 2 & 3
RS-13-065, Core Spray/Auto Depress'N System Relay Logic Panel
NRC 2002-0069, Filing of Owners Inservice Inspection Summary Report
RS-20-153, Amendment 29 to Fire Protection Report, Chapter 3, Guidelines of BTP Cmeb 9.5-1