ML20083R768
| ML20083R768 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 01/21/1974 |
| From: | Cobean W CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | James O'Reilly US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20083R766 | List: |
| References | |
| NUDOCS 8304040626 | |
| Download: ML20083R768 (1) | |
Similar Documents at Indian Point | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19352A1131974-06-21021 June 1974
[Table view]Ao:On 740620,electrical Feed to Fast Insertion Pulser Interrupted Due to Power Supply Failure & Protective Fuse Blowing.Cause Unknown.Power Supply & Fuses Replaced ML20083R6631974-02-19019 February 1974 AO 4-2-8:on 740215,during Reactor Coolant Temp Channel Test, Limiting Safety Sys Setting Read Below Required Tech Spec for Channels II & Iv.Cause Under Investigation ML20083R6871974-02-19019 February 1974 AO 4-2-7:on 740201,both Doors of Personnel Air Lock to Containment Bldg Opened at Same Time.Caused by Erroneous Operation of Hand Wheel Door Lock by Offsite Employee Which Triggered Failure of Interlock.Interlock Inspected ML20083R7101974-02-0808 February 1974 AO 4-2-6:on 740125,control Rods Did Not Withdraw from Core to Insertion Limit in Conformance W/Tech Specs.Boron Added to Coolant Sys & Procedures re-emphasized to Personnel ML20083R6961974-02-0606 February 1974 AO 4-2-7:on 740201,both Doors of Containment Air Lock Opened at Same Period of Time.Caused by Offsite Employee Mistakenly Operating Wrong Hand Wheel Opening Inner Air Lock Door ML20083R7291974-02-0505 February 1974 AO 4-2-5:on 740123,coolant Sys Pressure Transient Experienced During Reactor Coolant Start.Caused by Insufficient Amount of Nitrogen Added to Pressurizer. Nitrogen Procedure Changed ML20083R7611974-02-0404 February 1974 AO 4-2-4:on 740121,small Leak Observed at Base of Fillet Weld Attaching Pipe Nozzle to Orifice Flange for Flow Transmitter 946D.Dye Penetrant Insp Indicated Pipe Also Cracked.Faulty Weld Ground Out & Flange Socket Redressed ML20083R8961974-02-0101 February 1974 AO 4-2-3:insp Determined Snubber on Component Cooling Water Return Line & Snubber on Secondary Blowdown Line Defective. Cause Under Investigation.Snubbers Replaced ML20083R7181974-01-31031 January 1974 AO 4-2-6:on 740125,reactor Brought Critical W/Control Rods Below Required Insertion Limit.Cause Under Investigation ML20083R7401974-01-28028 January 1974 AO 4-2-5:on 740123,while Placing Reactor Coolant Pump in Svc,Coolant Sys Pressure Exceeded Tech Spec Limit.Probably Caused by Insufficient Nitrogen Vol ML20084A0141974-01-25025 January 1974 AO 4-2-2:limiting Safety Sys Settings of Channels I & III Discovered Below Tech Spec Requirement.Cause of Setpoint Drift Problem Under Investigation ML20083R7681974-01-21021 January 1974 AO 4-2-4:on 740121,small Leak Observed in Upstream Orifice Flange Connection for Flow Transmitter 946D in Return Line to Reactor Coolant Loop.Dye Penetrant Insp of Weld Will Be Made ML20083R9151974-01-21021 January 1974 AO 4-2-3:insp Completed on 740118 Revealed Accumulator Oil Level Plunger of Two Snubbers Below Criteria Mark.Cause of Failure Will Be Determined During Insp of Disassembled Defective Snubbers.Snubbers Replaced ML20084A0481974-01-18018 January 1974 AO 4-2-1:low Steam Line Pressure Bistables Found Below Required Limit of 600 Psig.Cause of Setpoint Drift Under Investigation.Bistable Recalibr ML20084A0261974-01-15015 January 1974 AO 4-2-2:limiting Safety Sys Settings of Channels I & III Found Below Tech Spec Requirement.Cause of Setpoint Drift Under Investigation ML20084A1411974-01-0808 January 1974 AO 4-2-1:low Steam Line Pressure Bistables Found Below Required Limit of 600 Psig.Cause of Setpoint Drift Under Investigation.Bistable Recalibr ML20084A1941974-01-0404 January 1974 AO 3-2-18:on 731219,analysis of Monthly Pressurizer Pressure Tests Indicated Low Setting for One Bistable.Bistable Recalibr & Sensitivity of Bistable Setpoints Under Investigation ML20084A2321973-12-28028 December 1973 AO 3-2-17:on 731217,one Bistable Setting Exceeded Tech Spec Limit of 92%.Cause of Setpoint Drift Under Investigation. Channel Recalibr ML20084A2071973-12-21021 December 1973 AO 3-2-18:on 731219,analysis of Monthly Pressurizer Pressure Tests Indicated Low Setting for One Bistable.Channel Recalibr & Detailed Rept Re Instrument Drift Underway ML20084A2521973-12-18018 December 1973 AO 3-2-17:on 731217,one Bistable Setting Exceeded Tech Spec Limit of 92% Span.Caused by Instrument Drift.Channel Recalibr & Investigation Initiated for Detailed Analysis of Instrument Capabilities ML20084A2961973-12-0303 December 1973 AO 3-2-16:on 731116,setting for One Bistable Associated W/ Low Pressurizer Pressure Safety Injection Did Not Reach Tech Spec Limit.Cause Not Yet Determined.Channel Recalibr ML20084A3111973-11-19019 November 1973 AO 3-2-16:on 731116,during Cold Shutdown,Setting for One Bistable Did Not Reach Tech Spec Requirement.Channel Recalibr ML20084A3351973-11-12012 November 1973 AO 3-2-15:during 731026 Insp,Leaks Observed at Socket Weld Branch Connections for Vents S-47 & S-51.Caused by Fatigue Failure of Pipe to Socket Welds.Metallurgical Exam Initiated,Vent Valve Assemblies Replaced & RCS Inspected ML20084A3811973-11-0101 November 1973 AO 3-2-14:on 731017,prior to Maint on Pressurizer Safety Valves,Lift Pressure Settings Exceeded Tech Spec Limit. Valves Disassembled,Inspected & Seat Surfaces Repaired ML20084A3481973-10-31031 October 1973 AO 3-2-15:during 731030 Insp,Leaks Observed at Socket Weld Branch Connections for Vents S-47 & S-51.Cause & Corrective Actions Will Be Provided Upon Completion of Exam ML20084A4381973-10-26026 October 1973 AO 3-2-13:on 731011,reactor Tripped Off Line Due to Loss of Generator Field Relay Action.Caused by Gaseous & Particulate Radioactivity in Auxiliary Bldg.Investigation Concluded That No Release to Atmosphere Occurred ML20084A3861973-10-19019 October 1973 AO 3-2-14:on 731017,set Pressure of Safety Valves Exceeded Tech Spec Limit.Valves Will Be Disassembled,Inspected & Seating Surfaces Repaired ML20084A4111973-10-12012 October 1973 AO 3-2-13:on 731011,reactor Tripped Off Line Due to Loss of Generator Field Relay Action.Caused by Gaseous & Particulate Radioactivity in Auxiliary Bldg.Samples Analyzed & Investigation Initiated ML20084A3901973-09-27027 September 1973 AO 3-2-12:on 730913,during Maint of Closure Mechanism of 80-ft Elevation Outer Door of Vapor Container,Inner Door Partially Opened for Short Period.Cause Unknown.Procedures Revised & Supplemented to Prevent Recurrence ML20084A4441973-09-0606 September 1973 AO 3-2-11:on 730822,discovered That Instrument Setting of One of Four Channels of Low Steam Line Pressure Controllers in High Steam Flow Safety Circuit Below Tech Spec Requirements.Caused by Instrument Drift.Channel Recalibr ML20084A4671973-08-23023 August 1973 AO 3-2-11:on 730822,instrument Setting for One Channel of Low Steam Line Pressure Controllers in High Steam Flow Safety Circuit Found Below Tech Spec Requirements.Caused by Instrument Drift.Channel Recalibr & Satisfactorily Tested ML20084A4961973-08-16016 August 1973 AO 3-2-10:on 730802,discovered That Limiting Safety Sys Setting of Channel III of overpower-overtemp delta-T Reactor Trip Circuitry Below Tech Spec Requirements.Caused by Improper Adjustment of Channel.Channel Recalibr ML20084A9691973-07-0303 July 1973 Telecopy AO 3-2-9:on 730702,first Stage Turbine Pressure Setting Discovered Slightly in Excess of Tech Spec Limits. Cause Unknown.Investigation Underway ML20084B0261973-06-11011 June 1973 AO 3-2-7:on 730601,one of Two Motor Actuators for MOV 851A Improperly Moved to Closed Position Following Initiation of Automatic Safety Injection as Result of Spurious Signal from High Steam Line Flow Logic.Caused by Logic Malfunction ML20084A9831973-06-0808 June 1973 Telecopy AO 3-2-8:on 730607,during Performance of Periodic Tests & Calibr Checks Re Reactor Coolant Flow,Flow Trip Settings Discovered Slightly Below Tech Spec Requirements. Cause Unknown.Investigation Underway ML20084B0391973-06-0101 June 1973 Telecopy AO 3-2-7:on 730601,during Power Level Testing, Spurious Safety Injection Signal Initiated Automatically Starting High Head Pumps.One of Two Valves Tying Discharges Driven to Closed Position.Cause Unknown ML20084A9921973-05-29029 May 1973 AO 3-2-6:on 730519,within Minutes After Starting High Head Safety Injection Pump 23,accumulator Level Observed Not Changing & Pump Discharge Pressure Decreased to Existing Rcs.Caused by Personnel Error ML20084B0131973-05-25025 May 1973 AO 3-2-5:on 730518,pressure Transient within RCS Experienced Due to Closure of Certain Air Operated Valves in Reactor Coolant Letdown Sys.Caused by Moisture Freezing in Air Supply Line Refrigerant Dryer of Instrument Air Sys ML20084B0981973-05-14014 May 1973 Ao:On 730511,during Pressurization,Preparatory to Starting Reactor Coolant Pumps for Performance of Hydrostatic Leak Test of Rcs,Leak Apparently Occured in Valve 204B Located in Loop 21 Charging Line.Caused by Defect in Stud Holes ML20084B1101973-05-0404 May 1973 Ao:On 730426,MSIV 22 Failed to Close in Response to Manual Signal by Control Room Operator.Caused by Binding of Linkage Connecting Solenoid Armature to Valve.Solenoids Thoroughly Cleaned of All Lubricant 1974-06-21 Category:TEXT-SAFETY REPORT MONTHYEARML20217H8501999-10-14014 October 1999
[Table view]Safety Evaluation Supporting Amend 197 to License DPR-64 ML20206U2551999-02-0909 February 1999 Safety Evaluation Supporting Amend 187 to License DPR-64 ML20236Y1571998-08-0303 August 1998 Part 21 Rept Re ASTM A351,GR. CF8 Matl at Indian Point Being Out of Specifications in Molybdenum & Chromium.Cause & Corrective Actions Are Not Stated ML20236V4281998-07-13013 July 1998 Safety Evaluation of TRs WCAP-14333P & WCAP-14334NP, PRA of RPS & ESFAS Test Times & Completion Times. Repts Acceptable ML20236T5511998-06-24024 June 1998 Consolidated Edison Co of Ny,Indian Point Unit 2,Drill Scenario Number 1998C ML20248B2371998-03-31031 March 1998 Revised Monthly Operating Rept for March 1998 for Indian Point Station Unit 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML1005008001997-02-28028 February 1997 Conditional Extension of Rod Misalignment TS for Indian Point 3. ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl ML20096E5101995-12-31031 December 1995 Resubmitted Rev 13 to QA Program 05000286/LER-1994-010, :on 941007,concluded That at Least Two EDGs Inoperable During June 1992 Surveillance Test of Carbon Dioxide Fire Protection Sys.Caused by Inadequate Procedural Guidance.Surveillance Test Revised1994-11-0707 November 1994
ML20248F3001988-12-31031 December 1988 10CFR50.59(b) Rept of Changes,Tests & Experiments Completed in 1988 ML20246E2711988-12-31031 December 1988 Con Edison 1988 Annual Rept ML20196D3011988-10-31031 October 1988 Reactor Vessel Matl Surveillance Program for Indian Point Unit 2 Analysis of Capsule V ML20155H2541988-09-30030 September 1988 Rev 2 to Indian Point Unit 2 (NRC Bulletin 88-008 Thermal Stresses in Piping Connected to RCS) Indentification of Unisolable Piping & Determination of Insp Locations ML20154M5661988-08-31031 August 1988 Monthly Operating Rept for Aug 1988 for Indian Point Station Unit 2 1999-02-09 |
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. .o 4 Irving Place, New York, N Y 10003 January 21, 1974 Re: Indian Point Unit No. 2 AEC Docket No. 50-247 Operating License DFR-26 A.O.-4-2-4 Mr. James P. O'Reilly, Director R2gulatory Operations, Region I U. S. Atomic Energy Commission 631 Park Avenue King of Prussia, Pennsylvania 19406 Denr Mr. O'Reilly, hnaccordancewiththerequirementsof.Section6.12.2aofthe Technical Specifications of Facility Operating License No. DPR-26, the following report is submitted.
During the course of a routine plant inspection on January 21, 1974 a small leak was observed at the upstream orifice flange connection for flow transmitter 946D in the six inch residual heat removal sys-tem return line (Line No. 355) to No. 21 reactor coolant loop. At the time of this observation, the reactor was in the cold shutdown condition with: the residual heat removal system in service and pres-curized to about 400 psig. .
The leak is at the base of the fillet weld attaching a 3/4" pipe nipple to the orifice flange and is on the pipe side of the weld.
Preparations for repair of the leak are underway; however, before repairs are initiated, a dye penetrant inspection of the weld will bn made to determine the nature and extent of the defect. In add-ition our Engineering Department is investigating the occurrence in an effort to detcrmine the cause.
Mr. Anthony Fasano of your office was notified on January 21, 1974 of the circumstances relating to this occurrence.
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Very truly yours, GNtk.tk b d0d4 1 Warren R. Cobean, Jr., Manager Nuclear Power Generation f
cc: Mr. John F. O' Leary
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8304040626 740204 PDR ADDCK 05000247 (D S PDR _
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