ML20216J733
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| ML20216J733 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 11/24/1978 |
| From: | Klingler G, Nolan F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| References | |
| PNO-78-195, NUDOCS 9804210472 | |
| Download: ML20216J733 (1) | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-I-97-053, on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR1997-08-22022 August 1997
[Table view]PNO-I-97-053:on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR PNO-I-90-094, on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured1990-10-17017 October 1990 PNO-I-90-094:on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured PNO-I-90-077, on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed1990-09-0707 September 1990 PNO-I-90-077:on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed PNO-I-90-065, on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days1990-08-15015 August 1990 PNO-I-90-065:on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days PNO-I-90-063, on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced1990-08-0909 August 1990 PNO-I-90-063:on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced ML20245G2181989-06-21021 June 1989 PNS-I-89-010:on 890621,Dept of Investigation in New York City Received Call Threatening Destruction of Plant & Ref 1977 Incident Where Damage Inflicted on Plant.Bomb Threat Contingency Procedures Implemented & Security Maintained PNO-I-88-065, on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals1988-06-20020 June 1988 PNO-I-88-065:on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals PNO-I-88-003, on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 8801051988-01-0707 January 1988 PNO-I-88-003:on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 880105 PNO-I-87-039, on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays1987-05-0101 May 1987 PNO-I-87-039:on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays PNO-I-87-025, on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days1987-03-26026 March 1987 PNO-I-87-025:on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days ML20207R1791987-03-0606 March 1987 PNS-I-87-003:on 870306,security Officer at Offsite Training Ctr in Toddville,Ny Received Bomb Threat by Telephone.Search of Site Produced Negative Results.Local Law Enforcement Agencies Responded.Security Measures Heightened PNO-I-87-010, on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown1987-02-12012 February 1987 PNO-I-87-010:on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown PNO-II-86-078, on 861021,2 Gallons of Hydrazine Spilled in Turbine Bldg.Caused by Leak in Deionized Water Mixing Valve Overflowing Mix Tank.Spill Cleaned Up1986-10-22022 October 1986 PNO-II-86-078:on 861021,2 Gallons of Hydrazine Spilled in Turbine Bldg.Caused by Leak in Deionized Water Mixing Valve Overflowing Mix Tank.Spill Cleaned Up PNO-I-86-084, on 861020,reactor Tripped.Caused by Failure of Safety Injection Logic Relay Which Demands Reactor Trip Upon Safety Injection Actuation.Difficulties Encountered W/Two of Three Auxiliary Feedwater Pumps1986-10-21021 October 1986 PNO-I-86-084:on 861020,reactor Tripped.Caused by Failure of Safety Injection Logic Relay Which Demands Reactor Trip Upon Safety Injection Actuation.Difficulties Encountered W/Two of Three Auxiliary Feedwater Pumps PNO-I-86-060, on 860806,vital Bus Normal Supply Breaker 6A Tripped Due to Indicated Bus Fault.Caused by Emergency Diesel Generator Supply Breaker Shorting Phase to Phase.Bus Repaired1986-08-0606 August 1986 PNO-I-86-060:on 860806,vital Bus Normal Supply Breaker 6A Tripped Due to Indicated Bus Fault.Caused by Emergency Diesel Generator Supply Breaker Shorting Phase to Phase.Bus Repaired PNO-I-86-049A, on 860706,forced Outage Entered When 18-inch Piece of Blade Foil from Low Pressure Turbine 1 Broke Off During Startup.Cause Unidentified.Options to Repair &/Or Replace Available Rotors Being Evaluated1986-07-23023 July 1986 PNO-I-86-049A:on 860706,forced Outage Entered When 18-inch Piece of Blade Foil from Low Pressure Turbine 1 Broke Off During Startup.Cause Unidentified.Options to Repair &/Or Replace Available Rotors Being Evaluated PNO-I-86-051, on 860718,plant Operator Contaminated While Assisting in Repair of Gasket Leak in Steam Environ.Caused by Removal of Required Wet Gear & Respirator When Operator Passed Out from Heat Prostration.Operator Hospitalized1986-07-18018 July 1986 PNO-I-86-051:on 860718,plant Operator Contaminated While Assisting in Repair of Gasket Leak in Steam Environ.Caused by Removal of Required Wet Gear & Respirator When Operator Passed Out from Heat Prostration.Operator Hospitalized PNO-I-86-049, on 860706,18-inch Piece of Blading from Low Pressure Turbine 31 Broke Off During Main Generator Startup. Turbine Vendor Evaluating Damage.Repair Expected to Take at Least 1 Wk1986-07-0707 July 1986 PNO-I-86-049:on 860706,18-inch Piece of Blading from Low Pressure Turbine 31 Broke Off During Main Generator Startup. Turbine Vendor Evaluating Damage.Repair Expected to Take at Least 1 Wk PNO-I-85-071, on 850927,Hurricane Gloria Located 50 Miles East of Cape May,Nj.Reactor Facilities Located Along Coast Implementing Procedures Per Emergency Plans.Listed Plants Shutting Down.Oyster Creek Reduced Power Levels to 35%1985-09-27027 September 1985 PNO-I-85-071:on 850927,Hurricane Gloria Located 50 Miles East of Cape May,Nj.Reactor Facilities Located Along Coast Implementing Procedures Per Emergency Plans.Listed Plants Shutting Down.Oyster Creek Reduced Power Levels to 35% PNO-I-85-043, on 850623,10 Indications of Unacceptable Size of Steam Generator Shell Transition Girth Weld Per ASME Section XI Found Through Ultrasonic Exam.Caused by pre-existing Flaws Present After 1983 Repairs1985-06-26026 June 1985 PNO-I-85-043:on 850623,10 Indications of Unacceptable Size of Steam Generator Shell Transition Girth Weld Per ASME Section XI Found Through Ultrasonic Exam.Caused by pre-existing Flaws Present After 1983 Repairs ML20197G9011984-06-14014 June 1984 PNS-I-84-011A:on 840613,licensee Provided Update on Status of Investigation Re Falsified Records of Employment Ltrs. Licensee Will Request Unions to Conduct Background Investigations Per ANSI 18.17 PNO-I-80-135, on 800924,both Containment Spray Pumps Discovered in pull-to-lock Position After Tagging by Operators Per Containment Entry Procedure.Switches Returned to Automatic Position & Change to Procedure Initiated1980-09-26026 September 1980 PNO-I-80-135:on 800924,both Containment Spray Pumps Discovered in pull-to-lock Position After Tagging by Operators Per Containment Entry Procedure.Switches Returned to Automatic Position & Change to Procedure Initiated ML20217B0321978-12-0707 December 1978 PNO-78-025:on 781207,licensee Commenced Plant Shutdown to Effect Repairs to One of Four Sgs.Primary to Secondary Sys Leak of 0.10 Gpm Indicated on 781206.No Release of Radioactivity to Environ Occurred ML20216J7331978-11-24024 November 1978 PNO-78-195:on 781124,small Leak Developed in Socket Weld on Drain Line from Seal Injection Headers to Reactor Pump.Leak Did Not Result in Any Radioactivity Release to Environ.State of Ny Informed ML20217B1941978-08-30030 August 1978 PNO-78-157:on 780829,leak Was Detected Upon Completion of Repairs to Manifold in Hydrogen Gas Storage Area & Small Explosion Occurred While Workers Tried to Stop Leak.State of New York & OSHA Informed.Region I Notified on 780830 ML20236E8181978-04-13013 April 1978 PNO-78-081:on 780413,Region I Informed by Licensee That Maint Workers March Film Badge Result Indicated Exposure of 3.11 Rem That Would Give Individual Quarterly Exposure of 4.47 Rem.State of New York Informed ML20248L2581978-03-23023 March 1978 PNO-78-060:on 780321,three Offsite Licensee Maint Workers Were Reassigned to Plant to Work in Radiation Areas.Refusal of Assignment Resulted in Discharge for One Worker.Worker Was Interviewed by Radio & Television on 780321 ML20249A8871977-11-22022 November 1977 PNS-77-047:on 771122,Westchester Business Ofc of Consolidated Edison Co,New York Received Telephone Call Re Bomb Threat from an Unidentified Male.Emergency Procedures in Effect.State of Ny Informed ML20249A9111977-08-0404 August 1977 PNS-77-030:on 770803,call Was Received Stating That Two Facilities Would Be Bombed.Bomb Threat Procedures Were Implemented.Site Was Searched & Threat Was Declared Over. Licensee Maintained Alert Status Through 770804 ML20151Y1081977-07-15015 July 1977 PNO-77-126B:on 770714,electrical Output Added to Distribution Sys at Indian Point Unit 3.Reactor Power Level Increased Throughout Night as Customers Incrementally Added to Sys.Nrc Inspector Witnessing Operation Repts ML20151X9981977-07-14014 July 1977 PNO-77-126A:Inspectors on Site Determined That IPS Unit 3 Safety Sys Functioned Properly Following Reactor Trip & During Nearly 6 Hour Loss of Offsite Power.Licensee Held Press Conference on 770714.Reactor to Be Brought Critical ML20151X6241977-07-14014 July 1977 PNO-77-126:on 770713,unit 3 Reactor Tripped from 91% Power Due to Lightning Strike & Resulting Fire at Buchanan,Ny Substation Located 1/2 Mile from Indian Point Site. Caused by Power Blackout ML20151X6531977-07-0505 July 1977 PNO-77-120:on 770702,unit Shutdown Due to RCP Seal Failure. Approx 40,000 Gallons of RCS Water Was Leaked Over Period of 8 H Into Containment Via Failed Seal While Unit Being Placed in Cold Shutdown Condition ML20236J8711976-09-27027 September 1976 PNS-76-055:on 760925,an Automobile Was Driven Through Double,Closed,Locked & Manned Main Vehicle Gate at Owner Controlled Perimeter,Resulting in Damage to Both Gates. Plant Guards Apprehended Driver ML20249B9481976-09-22022 September 1976 PNO-76-162:while Shutdown for Scheduled Maint Outage,Minor Leak Was Observed in Vicinity of factory-made Weld on Outlet Nozzle of Boron Injection Tank.Insp & Radiographs Confirmed That Weld Joining Pipe safe-end to Tank Was Defective ML20249B3301976-04-30030 April 1976 PNO-76-081:while Reactor Shutdown,Between Five & Ten Gallons of Nonradioactive Borated Water Inadvertently Sprayed Inside Containment.Caused by Operator Error Due to Improper Valve Lineup ML20249B3771976-04-0707 April 1976 PNO-76-066:on 760406,initial Criticality Achieved.Region I Inspectors at Site Reported That Actual Boron Concentration Was in Close Agreement W/Predicted Values.State of New York Informed & Press Release Planned by Licensee ML20249B2021976-03-17017 March 1976 PNO-79-043:on 760317,nonisolable Leak in RCS Was Identified During Post Core Load Hot Functional Testing.Rcs Being Cooled Down to Make Repairs.Cause of Leak Has Not Yet Been Determined ML20236F7991976-03-0101 March 1976 PNS-76-005A:on 760229, Citizens for Protection of Environ Held Planned Demonstration at Entrance to Licensee Facility. Counter Demonstration by United Utility Workers of America, Local 3 Also Held at Same Time.No Physical Clash Occurred ML20236F2511976-02-24024 February 1976 PNS-76-005:on 760224,licensee Advised That Citizens for Protection of Environ Petitioned Buchanan,New York Police Dept for Permit to Demonstrate at Entrance to Facility on 760229.Permit Granted ML20249B2461976-01-23023 January 1976 PNO-76-012:on 760121 & 22,fish Mortality on Intake Screens of CWS Was 12,799 & 18,233 Respectively.One of Five Operating Circulating Water Pumps Was Shutdown to Reduce Mortality.State of Ny Informed ML20236U9221975-11-0505 November 1975 PN-75-118:on 751101-03,fish Mortality on Intake Screens of Circulating Water Sys Exceeded Environ TS Action Level of 5000 Per Day on Three Consecutive Days.Two Circulating Water Pumps Were Shutdown on 751103 & One Was Shut Down on 751104 ML20236V1051975-10-20020 October 1975 PN-75-110:on 751016,unplanned Shutdown Instituted,Due to Electrical Fault in Main Generator.Short Found in C Phase, Apparently Caused by Metal Cylinder Found Lodged in Windings.Duration of Shutdown Not Yet Established ML20236U8561975-09-26026 September 1975 PN-75-098:on 750926,guard Received Call from Onsite Extension That Bomb Was in Plant.Bomb Threat Procedures Were Instituted.No Bomb Found ML20236T9821975-06-25025 June 1975 PN-75-041:for Several Weeks,Westinghouse Has Been Repairing Cladding Cracks in Sgs.Cracks Apparently Caused by Saltwater Intrusion Which Occurred When Generators Were Shipped by Barge Several Years Ago ML20236T9921975-06-18018 June 1975 PN-75-038:on 750617,fire Occurred in Temporary Const Bldg at Site.Ofc Equipment,Benches & Boxes of Insulation Destroyed. State of Ny Informed ML20236U2341975-06-0202 June 1975 PN-75-030:on 750602,Insp & Enforcement Ofc Was Informed That Reactor Tripped from Loss of 1 Source of Offsite Power. Janitor Was Found on Small Parapet W/Serious Burns Over Portion of Body & Has Been Hospitalized ML20236U0171975-04-16016 April 1975 PN-75-011:on 750416,licensee Reported That Bomb Threat Called Into New York Daily News Newspaper,To Effect That Three Bombs Placed at Two Power Plants of Consolidated Edison Co.No Bombs Found 1997-08-22 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000003/19980191999-03-0909 March 1999
[Table view]Insp Rept 50-003/98-19 on 981130-990222.No Violation Noted. Major Areas Inspected:Review of Facility Mgt & Control ML20237D1381998-08-19019 August 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Between 971024 & 980528,licensee Failed to Assure That Design Change in Oct 1997 Subject to Design Control Measures ML20236M6011998-07-0606 July 1998 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:On 970808,double Verifications of Steps 3.4.1 & 3.5.2 of PT-W1,which Involved Checks of DG Compressor,Not Performed,But Records Created ML20154Q1951998-01-22022 January 1998 Partially Deleted Investigation Rept 1-97-038.Noncompliance Noted.Major Areas Investigated:Falsification of Surveillance Test Records by Nuclear Production Technician ML20217H3531997-10-0707 October 1997 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000.Violation Noted:Con Edison Did Not Operate within Restrictions of TS Figure 3.1.A-3,in That Pressurizer Level Was Greater than 30% PNO-I-97-053, on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR1997-08-22022 August 1997 PNO-I-97-053:on 970826,special Security Insp Will Be Performed,That Will Examine Security Activities at Vermont Yankee,Pilgrim & Indian Point 3.Team Will Include Security Specialists from Region I & NRR ML20217R3361997-08-19019 August 1997 NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Violation Noted:Measures Were Not Established to Assure That Applicable Regulatory Requirements & Design Basis,Were Correctly Translated Into EOPs IR 05000247/19930261993-11-23023 November 1993 Insp Rept 50-247/93-26 on 931108-12.No Violations Noted. Major Areas Inspected:Mgt Support Plans,Protected & Vital Area Physical Barriers,Detection & Assessment Aids,Protected & Vital Area Access Control of Personnel IR 05000286/19930161993-10-19019 October 1993 Insp Rept 50-286/93-16 on 930802-06 & 0920-24.No Violations Noted.Major Areas Inspected:Isi Program,Procedures,Scope of ISI Work for Outage,Current Insp Plan & Testing Procedures IR 05000286/19930211993-09-17017 September 1993 Insp Rept 50-286/93-21 on 930830-0902.No Violations Noted. Major Areas Inspected:Mgt Support & Audits,Protected & Vital Area Physical Barriers,Detection & Assessment Aids & Protected Vital Area Access Control of Personnel PNO-I-90-094, on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured1990-10-17017 October 1990 PNO-I-90-094:on 901016,transfer of Fuel Assemblies Stuck in Upper Core Internals.No Apparent Damage to Dropped Fuel Assembly Occurred.Recovery Operations Secured PNO-I-90-077, on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed1990-09-0707 September 1990 PNO-I-90-077:on 900906,unplanned Shutdown Greater than 48 H Occurred Due to RCS Packing Leak from Pressurizer Spray Valve.Plant Placed in Hot & Cold Shutdown.Licensee Activities Monitored & State of Ny Informed PNO-I-90-065, on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days1990-08-15015 August 1990 PNO-I-90-065:on 900814,licensee Reported That Licensed Reactor Operator Tested Positive for Marijuana as Result of Random Fitness for Duty Test.Operator Unescorted Site Access Suspended for 14 Days PNO-I-90-063, on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced1990-08-0909 August 1990 PNO-I-90-063:on 900809,plant Shutdown Due to Potential Loss of Three Emergency Diesel Generators.Caused by Blown Control Power Fuse.Fuse Replaced ML20247K5281989-09-14014 September 1989 EN-89-086:on 890919,notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Will Be Issued to Licensee Based on Security Violations Re Access Control & Illumination in Protected Area ML20247B9531989-08-24024 August 1989 Enforcement Conference Rept 50-286/89-15 on 890808.Major Areas Discussed:Security Program During Spring 1989 Plant Outage IR 05000286/19890151989-07-24024 July 1989 Partially Withheld Physical Security Insp Rept 50-286/89-15 on 890605-07 (Ref 10CFR73.21).Violations Noted Re Physical Barriers,Vital Areas & Access Controls.Major Areas Inspected:Detection & Assessment Aids & Alarm Stations ML20245G2181989-06-21021 June 1989 PNS-I-89-010:on 890621,Dept of Investigation in New York City Received Call Threatening Destruction of Plant & Ref 1977 Incident Where Damage Inflicted on Plant.Bomb Threat Contingency Procedures Implemented & Security Maintained IR 05000286/19890031989-06-13013 June 1989 Enforcement Conference Rept 50-286/89-03 on 890428 in King of Prussia,Pa Re Findings of Insp Repts 50-286/89-03 & 50-286/88-22.Violations Noted.Areas Discussed:Security Program During Current Outage ML20247A1051989-05-0909 May 1989 Notice of Violation from Insp on 890228-0417.Violation Noted:Technicians Failed to Secure Pump When Vibration Level Observed on Pump Motor Exceeded Procedural Limit of 3.5 Mils ML20247A0681989-05-0505 May 1989 Notice of Violation from Insp on 890314-25.Violation Noted: Workers Allowed to Enter High Radiation Areas W/O Being Provided or Accompanied by Individual Authorized in Radiation Protection Procedures IR 05000286/19890051989-04-11011 April 1989 Partially Withheld Physical Security Insp Rept 50-286/89-05 on 890227-0303 (Ref 10CFR73.21).Violations & Noncompliances Noted.Major Areas inspected:non-routine Event,Mgt Support, Security Program Plans & Audits & Physical Barriers ML20154Q7231988-09-21021 September 1988 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $75,000.Violations Noted:Qualification of Containment high-range Radiation Monitors Cable Connector Assembly Deficient PNO-I-88-065, on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals1988-06-20020 June 1988 PNO-I-88-065:on 880617,unit Tripped Due to High Water Level in Steam Generator 22.Caused by Contractor Cleaner Inadvertently Activating Boiler Feed Pump.Licensee Elected to Enter Cold Shutdown to Repair Connoseals IR 05000247/19880121988-05-24024 May 1988 Physical Security Insp Rept 50-247/88-12 on 880407.No Noncompliance Noted.Major Areas Inspected:Program for Protection of Safeguards Info,Per 10CFR73.21,including Use of Required Storage Repositories & Handling Procedures IR 05000286/19880061988-05-19019 May 1988 Physical Security Insp Rept 50-286/88-06 on 880412-14.No Noncompliance Noted.Major Areas Inspected:Plan & Implementing Procedures,Organization,Program Audits,Testing & Maint,Physical Barriers & Security Sys Power Supply PNO-I-88-003, on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 8801051988-01-0707 January 1988 PNO-I-88-003:on 880101,steam Generator (SG) 23 Boiled Dry During Plant Heatup.Cause Not Stated.On 880104,station Mgt Started Evaluating Safety Significance of Event & Best Method to Refill Generator.Sg 23 Refilled on 880105 IR 05000286/19870131987-08-21021 August 1987 Safety Sys Outage Mod Insp Rept 50-286/87-13 on 870422-0714. Rept Describes Activities & Findings Associated W/First Portion of Team Insp Re Outage Design Insp IR 05000247/19870141987-06-0808 June 1987 Emergency Preparedness Insp Rept 50-247/87-14 on 870512-14. No Violations Identified.Major Areas Inspected:Licensee Annual Emergency Exercise Performed on 870513 IR 05000286/19870111987-05-14014 May 1987 Insp Rept 50-286/87-11 on 870420-24.No Violations Noted. Major Areas Inspected:Radiological Effluents Control Program,Mgt Controls,Air Cleaning Sys,Program Implementation & Previously Identified Items IR 05000286/19870091987-05-11011 May 1987 Insp Rept 50-286/87-09 on 870402-03.No Violations Noted. Major Areas Inspected:Nuclear Matl Control & Accounting, Including Organization & Operating,Shipping & Receiving, Storage & Internal Control & Records & Repts PNO-I-87-039, on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays1987-05-0101 May 1987 PNO-I-87-039:on 870430,licensee Identified Potential Circuit Failure Preventing Automatic Start of Auxiliary Feedwater Pumps by Loss of Main Feedwater or lo-lo Steam Generator Signals.Circuit Modified for Independent Relays IR 05000286/19870031987-04-12012 April 1987 Exam Rept 50-286/87-03OL on 870224-26.Exam Results:Seven Senior Operator Candidates Passed All Portions of Exams.One Candidate Failed All Portions PNO-I-87-025, on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days1987-03-26026 March 1987 PNO-I-87-025:on 870326,licensee Announced Plans to Shut Down Reactor on 870327 Due to Steadily Increasing Leakage on Reactor Coolant Pump Seal.Caused by Degraded Seal.Shutdown Expected to Last 10 Days IR 05000286/19870021987-03-18018 March 1987 Insp Rept 50-286/87-02 on 870127-29.No Violations Noted. Major Areas Inspected:Dosimetry Staffing & Training, Facilities & Equipment Procedures,Dose Assessment QA & Documentation & Recordkeeping IR 05000247/19870041987-03-16016 March 1987 Insp Rept 50-247/87-04 on 870203-0302.No Violations Noted. Major Areas Inspected:Routine Daily Insps,As Well as Unscheduled Backshift Insps of Onsite Activities,Operations, Maint,Surveillance & Review of Periodic & Special Repts ML20207S3401987-03-11011 March 1987 Notice of Violation from Insp on 870127-29 IR 05000247/19870021987-03-10010 March 1987 Insp Rept 50-247/87-02 on 870127-29.Violation Noted:Failure to Include Acceptance Limits for Battery Electrolyte Temp & Failure to Ensure Battery Room Temp within Normal Bounds ML20207R1791987-03-0606 March 1987 PNS-I-87-003:on 870306,security Officer at Offsite Training Ctr in Toddville,Ny Received Bomb Threat by Telephone.Search of Site Produced Negative Results.Local Law Enforcement Agencies Responded.Security Measures Heightened IR 05000286/19870011987-03-0505 March 1987 Insp Rept 50-286/87-01 on 870106-0217.Major Areas Inspected: Plant Operations Including Shift Logs & Records,Reactor Trips/Engineered Safeguards Actuation,Surveillance,Maint & Followup to Generic Ltr 83-28 & TMI Action Items ML20212J3921987-03-0202 March 1987 Notice of Violation from Insp on 870106-0202 IR 05000247/19870011987-02-26026 February 1987 Insp Rept 50-247/87-01 on 870106-0202.Violation Noted:No post-maint (Mod) Test Performed After Changing Location of Emergency Diesel Generator Svc Water Flow Indication & Control Instruments PNO-I-87-010, on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown1987-02-12012 February 1987 PNO-I-87-010:on 870211,reactor Scrammed from Full Power During Transient Initiated by Loss of Instrument Bus.Safety Injection Signal Received on High Steam Flow Coincident W/Low Steam Line Pressure.Plant Stabilized in Hot Shutdown ML20210V6021987-02-10010 February 1987 Notice of Violation from Insp on 861215-19 IR 05000286/19860241987-02-0909 February 1987 Insp Rept 50-286/86-24 on 861215-19.Violation Noted:Raychem Splices Identified W/Less than Required 2-inch Overlap & Bending Radii Less than Allowed IR 05000247/19860331987-01-27027 January 1987 Radiation Protection Insp Rept 50-247/86-33 on 861215-19.No Violations Noted.Major Areas Inspected:Alara,Internal Exposure Control & External Exposure Control ML20213A4821987-01-22022 January 1987 Notice of Violation from Insp on 861116-870105 IR 05000247/19861361987-01-21021 January 1987 Meeting Rept 50-247/86-136 on 861209.Major Items Discussed: Plans for Integrated Assessment of Auxiliary Feedwater Sys. Mods Being Considered Include Providing Direct Indication of Overspeed Trip Mechanism Status in Control Room ML20212K3521987-01-20020 January 1987 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000 Based on 860811-0922 Insp.Violation Noted:Reactor Heated Up Above 200 F W/Both Recirculation & Containment Spray Pumps Inoperable IR 05000286/19860231987-01-15015 January 1987 Onsite Regular & Backshift Insp Rept 50-286/86-23 on 861118- 870105.Violation Noted:Failure to Follow Administrative Procedures AP-6 & AP-25-3 Re Work Requests & Matl Substitutions,Respectively 1999-03-09 |
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PRELIMINARY NOTIFICATION <
A. November 24, 1978 l }
PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-78-195 This preliminary notification ' constitutes EARLY notice of event of POSSIBLE safety or public interest significance. The information presented is as initially received without verification or evaluation and is basically all that is known by IE staff on this date.
Facility: Consolidated Edison. Company of New York, Inc'.
Indian Point Unit 2 (DN 50-247)
Subject:
UNSCHEDULED SHUTDOWN TO REPAIR LEAK ON SEAL INJECTION LINE TO REACTOR COOLANT PUMP A small leak developed in a socket weld on a drain line from the seal injection headers to the reactor coolant pump. Corrective maintenance to effect repairs includes draining the reactor coolant water to an elevation below the pump seals and is expected to require a facility shutdown of one week. The leak did not result in any radioactivity release to the ,
environment. '
Media interest is not expected. The State of New York has been informed. #
A press release is not planned by the licensee or NRC. ;
e t
' ) NRC, Region I, (Philadelphia) received no'tification of this occurrence by j telephone from the licensee at 10:50 a.m., on November 23, 1978. !
Contact:
FNolan, IE x28019 GKlingler, IE x28019 Distribution: Transmitted H St ll'.k Chairman Hendrie Commissioner Bradford S. J. Chilk, SECY Commissioner Kennedy Commissioner Ahearne C. C. Kammerer, CA Commissioner Gilinsky (For Distribution)
Transmitted: MNBLil*L -9 L. V. Gossick, EDO P. Bldg; ll @ J. G. Davis, IE S. H. Hanauer, ED0 H. R. Denton, N1R R. C. DeYoung, NRR Region 1 I)M J. J. Fouchard, PA R. J. Mattson, NRR N. M. Haller, MPA V. Stello, NRR (MAIL)
R. G. Ryar., OSP R. S. Boyq, NR J. J. Cummings, 0IA H. K. Shapar, ELD SS Bldg il' S C R. Minogue, SD
, C. V. Smith, NMSS ,
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9804210472 781124 PDR I&E PNO-78-195 PDR
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