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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20096H2301992-05-21021 May 1992
Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested
ML20235V5931989-03-0202 March 1989
Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed
ML20210L6591986-04-11011 April 1986
Ro:On 860328,diesel Fire Pump Tripped & Would Not Restart During Repair of 860327 Fire Pump Leak.Fire Watches Established.Temporary Bypass Installed.Work Deferred on 860410 & Will Resume Late Apr
ML20203P5411986-04-0707 April 1986
Ro:On 860311,fire Pump Taken Out of Svc to Perform Maint on Fire Main Supplied by Pump.Pump Out of Svc Beyond 7-day Limit Permitted by Tech Specs.Pump Will Be Returned to Svc in Approx 45 Days,Upon Completion of Repair Work
ML20203P3461986-03-31031 March 1986
Ro:On 860328,diesel Fire Pump Tripped & Could Not Be Restarted.Fire Booster Pumps 11 & 12 Also Out of Svc.Cause Not Stated.Fire Booster Pump 12 & Diesel Fire Pump Returned to Svc
ML20151R2921986-01-0303 January 1986
Ro:On 851127,high Pressure Water Protection Sys Fire Pump II Taken Out of Svc in Excess of 7-day Tech Spec Limit.Caused by Maint to Fire Main Supplied by Pump.Pump & Fire Main Returned to Svc on 851220
ML20137Q0251986-01-0202 January 1986
Ro:On 851219,post-maint Test Following Replacement of Fire Detection Alarm Terminal Block for Fan Cooler Unit 21 Not Performed.Caused by Personnel Oversight.Test Performed & Circuitry Repaired & Tested Successfully
ML20151R4421985-11-0101 November 1985
Ro:On 850920,Halon Sys Rendered Inoperable in Excess of 14-day Tech Specs Limit.Caused by Closure of Control Bldg Dampers Following Transformer Chart & Actuation of Deluge Sys.Fusible Links Replaced & Dampers Restored on 851030
ML20101A6881984-11-16016 November 1984
Special Rept:On 841017,work Began to Make Openings in Several Penetration Fire Barriers to Execute Various Mods During Scheduled Maint/Insp Outage.Fire Watches Posted When Openings Existed
ML20082R5531983-11-30030 November 1983
RO 83-43:two Independent Nonautomatic,Motor Operated Isolation Valves on Containment Spray Pump Discharge Pipes Found Closed & Deenergized Instead of Open & Deenergized,As Required.Caused by Operator Error.Valves Opened
ML20082S6021983-10-17017 October 1983
Telecopy RO 50-286/83-006:on 831017,steel Plates Holding Seismic Restraint Collars Discovered Not in Place.Work Request Issued to Correct Condition Prior to Plant Returning to Svc
ML20082S5961983-10-12012 October 1983
Telecopy RO 50-286/83-005:on 831011,drain Lines on Accumlators Determined Connected by Manual Valve.Caused by Design Error.Nonseismic Line Could Fail During Earthquake. Procedures Revised to Maintain Valve Closure
ML20090H3621983-10-0505 October 1983
Ro:On 831004,138-kV Station Auxiliary Power Supply Lost When Pilot Wire Receiver Relay Tripped.Cause Under Investigation. Supply Reestablished to All 6.9-kV Buses.Also Reported Per Part 21
ML20076G3031983-08-0101 August 1983
Ro:On 830729,review of Log Sheets Determined Isolation Valve Seal Water Sys Violated Tech Specs.Corrective Action Taken to Assure Locally Indicated Pressure on Tank Maintained Per Tech Specs
ML20069A7781983-03-0202 March 1983
Ro:On 830301,shaft Matl Found in Square Motor Housing RHR Pump 22 Was Carbon Steel Instead of Stainless Steel.Change Does Not Involve Unreviewed Safety Question Based on Use for Fewer than 24 Calender Months.Equipment Will Be Replaced
ML20083Q5091983-02-14014 February 1983
RO 83-003:on 830213,RCS Leakage from Packing on Valve 731 Exceeded Tech Spec Limit.Subsequent Analysis After Hot Shutdown Determined Leakage to Be within Tech Specs.Also Reported Per 10CFR21
ML20066G7691982-11-0909 November 1982
Ro:On 821108,upper End Plug from One Fuel Rod Found Lodged Between Upper End Plugs of Adjacent Fuel Rods within Assembly.Affected Assembly Will Not Be Returned to Core for Cycle 6.Also Reportable Per Part 21
ML20063B6511982-08-18018 August 1982
RO 82-32:on 820817,steam Generator 22 Blowdown Outer Isolation Valve CV1215A Closed.Caused by Failure of 1315A Solenoid Valve.Jumper Installed in Instrument Air Sys to Establish Blowdown.Also Reportable Per Part 21
ML20055B6011982-07-14014 July 1982
Telecopy Message of Ro:On 820713,while in Cold Shutdown During Refueling Outage,Testing of Pressurizer Safety Valves Indicated Setpoints for Pressure Control Valves 466 & 468 Below Tech Spec Limit
ML20054L1441982-06-21021 June 1982
Ro:On 820520,Fire Pump 12 Removed from Svc to Repair Leaking Packing Gland.Pump Overhauled & Leaks Repaired.Pump Returned to Svc on 820527
ML20054J2391982-06-10010 June 1982
Ro:During Scheduled Sample Collection for May 1982,Windsor Farms Environ Sampling Station 51 Ceased Commercial Milk Production.Potential Replacement Locations Are Being Investigated
ML20054F5441982-06-0909 June 1982
Ro:Provides Addl Info Re 820601 Diver Exposure in Excess of Limits.Review Conducted of Instrumentation Used in Radiation Surveys of Pool Immediately Prior to Exposure.One Alarming Dosimeter Used by Divers Found Inoperable
ML20054F5981982-06-0202 June 1982
Ro:On 820601,contractor Employee Experienced Personal Exposure Rate of 8.6 Rem While Working in Spent Fuel Pool. Encl Withheld (Ref 10CFR2.790)
ML20084B1171973-04-20020 April 1973
Telecopy Ro:On 730419,both Doors of 80-ft Elevation Personnel Air Lock to Containment Bldg Inadvertently Opened at Same Time.Caused by Interlock Malfunction.Investigation Ensuing
ML20084T7381972-10-24024 October 1972
Telecopy Ro:On 721020,while Making Monthly Surveillance Calibr on Offgas Monitor,Trip Setting on One Monitor Found Greater than Tech Spec Limits.Cause Not Stated
1992-05-21
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Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8501999-10-14014 October 1999
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
ML17059A3611994-07-0606 July 1994
Emergency Action Level Verification & Validation Rept.
ML17311A0181994-05-13013 May 1994
New York State EAL Upgrade Project Verification & Validation Rept.
ML20029C7801994-03-31031 March 1994
Monthly Operating Rept for Mar 1994 for Indian Point Unit 1. W/940415 Ltr
ML20056E5171993-08-31031 August 1993
Technical Review Rept, Tardy Licensee Actions
ML20062J2281993-07-23023 July 1993
Consolidated Edison Co of Ny Indian Point Unit 2,Drill Scenario 1993
ML20118A2681992-12-31031 December 1992
Consolidated Edison Co of Ny Indian Point,Unit 2 Exercise Scenario,1992
ML20125C7161992-12-0707 December 1992
Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl
ML20127P5861992-11-23023 November 1992
Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl
ML20096H2301992-05-21021 May 1992
Special Rept:On 920504,south Side Lower Electrical Tunnel Detection Sys 8 Taken Out of Svc for Mod to Reposition Detection Sys Run of Conduit.Detection Sys Declared Operable on 920520 After Mod Completed & Sys Retested
ML20079F9181991-05-31031 May 1991
Structural Evaluation of Indian Point,Units 2 & 3 Pressurizer Surge Lines,Considering Effects of Thermal Stratification
ML20059E9461990-08-31031 August 1990
Nonproprietary Rev 2 to Indian Point 2 Tube Fatigue Reevaluation
ML20059G2011990-07-31031 July 1990
Final Rept on Steam Generator Insp, Repair & Restoration Efforts During 1990 Midcycle Insp
ML20058K4151990-06-30030 June 1990
Steam Generator Insp,Repair & Restoration Program Presentation to Nrc
ML20058K4121990-06-30030 June 1990
Status Rept,Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to Nrc
ML20043A4891990-05-30030 May 1990
Nonproprietary Indian Point Unit 2 Steam Generator Insp, Repair & Restoration Program.
ML20042F1441989-12-31031 December 1989
New York Power Authority Annual Rept for 1989. W/900430 Ltr
ML19332B9371989-11-30030 November 1989
Nonproprietary Info Presented to NRC Re Indian Point Unit 2 Steam Generator Secondary Side Loose Objects.
ML19332D6661989-10-31031 October 1989
Nonproprietary Rev 2 to Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage.
ML20247J8161989-07-31031 July 1989
Safety Evaluation for UHS Temp Increase to 95 F at Indian Point Unit 3
ML20248B3171989-06-30030 June 1989
Rev 1 to Nonproprietary WCAP-12294, Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept,Spring 1989 Outage
ML20248D3631989-06-30030 June 1989
Rev 1,to Indian Point Unit 3 Reactor Vessel Fluence & Ref Temp PTS Evaluations
ML20247N5331989-05-31031 May 1989
Nonproprietary Indian Point Unit 2 Steam Generator Girth Weld/Feedwater Nozzles Rept Spring,1989 Outage
ML20247J8071989-05-31031 May 1989
Containment Margin Improvement Analysis for Indian Point Unit 3
ML20247G5171989-04-30030 April 1989
Monthly Maint Category I Rept Pages from Monthly Operating Rept for Apr 1989 for Indian Point
ML20244C3311989-04-10010 April 1989
Safety Evaluation Supporting Amend 137 to License DPR-26
ML20248F4211989-03-31031 March 1989
NSSS Stretch Rating-3,083.4 Mwt Licensing Rept
ML20235V5931989-03-0202 March 1989
Special Rept:During Cycle 6/7 Refueling Outage Scheduled from Feb-May 1989,openings Will Be Made in Plant Penetration Fire Barriers in Order to Install Various Mods. Fire Watches Posted & Fire Detection Tests Completed
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
ML20154M5691988-07-31031 July 1988
Revised Page to Monthly Operating Rept for Jul 1988 for Indian Point Station Unit 2
ML20151N7881988-07-31031 July 1988
Rev 1 to Charpy Toughness & Brittle Transition Temp Characterization of HAZ High Hardness Zone of Indian Point Unit 2 Steam Generator Girth Weld by Gleeble Weld Thermal Cycle Simulation
ML20006B4741988-05-31031 May 1988
Nonproprietary Indian Point Unit 2 Evaluation for Tube Vibration Induced Fatigue.
ML20151N7821988-05-31031 May 1988
Fracture Sensitivity Study of Girth Weld 6 Repaired Configuration,Indian Point Unit 2
ML20153F9161988-04-28028 April 1988
Changes,Tests & Experiments - 1986
ML20151T4681988-01-31031 January 1988
Experimental & Finite Element Evaluation of Spent Fuel Rack Damping & Stiffness
1999-02-09
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Text
CharCO C. Jackson Vce Pres' dent Consohdated Edison Company of New York. Inc, lod.an Point Station Broadway & Bleakiey Ave .
Buchanan, NY 10511 Teiephone (914) 737-8116 November 9, 1982 Re: Indian Point Unit No. 2 Docket No. 50-247 Mr. Ronald C. Haynes, Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406
Dear Mr. Haynes:
In accordance with the Technical Specifications of Facility Operating License No. DPR-26, the following confirms notification on November 8, 1982 to Mr. Peter Koltay of your office, by Mr. Michael Blatt of Consolidated Edison of a Reportable Occurrence LER 82-045. This event is the type defined in Technical Specification, Section 6.9.1.7.1.c.
The Cycle 5/6 spent fuel inspection program includes a video examination of fuel assemblies scheduled to be returned to the core for Cycle 6. As a result of the review of videotapes of fuel assembly F-44, Con Edison was informed by Westinghouse at 3:25 p.m. on November 8 that an upper end plug from one fuel rod was observed to be lodged betwe(~ the upper end plugs of adjacent fuel rods within this assembly. The end spring for the affected fuel rod was visible, extending cut of the top of the rod, indicating that the fuel pellets remained contained inside the rod. No other significant anomalies were observed for this assembly.
The affected assembly will not be returned to the core for Cycle 6.
Consolidated Edison believes that this report also satisfies the requirements l of 10 CFR Part 21.
Very truly your /
/ ,
cc: Mr. William Mcdonald, Director (2 copies)
Office of Management Information and Program Control c/o Distribution Services Branch, DDC, ADM U.S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. T. Foley, Senior Resident Inspector U.S. Nuclear Regulatory Commission P. O. Box 28 Buchanan, New York 10511 8211230043 821109 PDR ADOCK 05000247 S PDR
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