ML20203P541
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| ML20203P541 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 04/07/1986 |
| From: | Selman M CONSOLIDATED EDISON CO. OF NEW YORK, INC. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8605070419 | |
| Download: ML20203P541 (1) | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20096H2301992-05-21021 May 1992
[Table view]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 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 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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CVuo PieiiderG Consolidated Edison Company of New York, Inc.
. Indian Point Station Broadway & B!eakley Ave, Buchanan, NY 10511 Telephone (914) 737-8116 April 7, 1986 Re: Indian Point Unit No. 2 Docket No. 50-247 Dr. Thomas E. Murley Regional Administrator U.S. Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406
SUBJECT:
Inoperable High Pressure Water Protection System 30-day Report
Dear Dr. Murley:
Technical Specification 3.13.A.2 requires that a 30-day report be submitted if a motor driven fire pump - is inoperable for greater than 7 days. This report is being submitted in accordance with this requirement.
On March 11, 1986, No. 11 fire pump was taken out of service to perform necessary maintenance on a section of the fire main supplied by this pump.
The fire pump remained out of service beyond the 7 day period permitted by.
the Technical Specifications. The scope of the maintenance planned requires approximately 45 days. The pump will be returned to service upon completion of repair work.
Very truly yours, fp '
17.250.4.3.1 cc: Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 38 Buchanan, NY 10511 8605070419 860407 i PDR ADOCK0500g7 4
. &7 8 0-
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