ML20151X657
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| ML20151X657 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 07/07/1977 |
| From: | Klingler G, Nolan F, Sniezek J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| PNO-77-123, NUDOCS 9809170201 | |
| Download: ML20151X657 (1) | |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-I-99-022, on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions1999-05-11011 May 1999
[Table view]PNO-I-99-022:on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions PNO-I-99-016, on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve1999-04-0707 April 1999 PNO-I-99-016:on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve PNO-I-99-006, on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys1999-01-29029 January 1999 PNO-I-99-006:on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys PNO-I-99-004, on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review1999-01-20020 January 1999 PNO-I-99-004:on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review PNO-I-99-001, on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power1999-01-0404 January 1999 PNO-I-99-001:on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power PNO-I-98-062, on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch1998-12-15015 December 1998 PNO-I-98-062:on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch PNO-I-98-039, 980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 9808111998-08-12012 August 1998 PNO-I-98-039:980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 980811 PNO-I-98-026, on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release1998-07-0101 July 1998 PNO-I-98-026:on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release PNO-I-98-025, on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting1998-06-30030 June 1998 PNO-I-98-025:on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting PNO-I-97-071, on 971124,licensee Announced Some Senior Level Mgt Changes.Ns Carns Resigned as Chief Nuclear Officer of Northeast Nuclear Energy Co,Effective 971201.Press Release Was Issued1997-11-24024 November 1997 PNO-I-97-071:on 971124,licensee Announced Some Senior Level Mgt Changes.Ns Carns Resigned as Chief Nuclear Officer of Northeast Nuclear Energy Co,Effective 971201.Press Release Was Issued PNO-I-90-041A, on 900509,75 Gallons of Contaminated Water Spilled Out of TN-RAM Cask & Into Trench.Cask Should Contain No free-standing Liquid.Cask Placed in Secured Parking Area within Burial Site.State of CT Notified1990-04-10010 April 1990 PNO-I-90-041A:on 900509,75 Gallons of Contaminated Water Spilled Out of TN-RAM Cask & Into Trench.Cask Should Contain No free-standing Liquid.Cask Placed in Secured Parking Area within Burial Site.State of CT Notified PNO-I-89-080, on 890922,NRC Presented Preliminary Results of Requalification Exams Indicating Failure of Two Crews. Licensee Preparing Justification for Continued Operation for Region I Mgt Review1989-09-22022 September 1989 PNO-I-89-080:on 890922,NRC Presented Preliminary Results of Requalification Exams Indicating Failure of Two Crews. Licensee Preparing Justification for Continued Operation for Region I Mgt Review PNO-I-89-076, on 890906,contaminated Equipment Located in Unrestricted Areas.Equipment Included Hydrolaze Unit & Tools.Licensee Initiated Survey as Result of Ongoing Internal Assessment1989-09-0707 September 1989 PNO-I-89-076:on 890906,contaminated Equipment Located in Unrestricted Areas.Equipment Included Hydrolaze Unit & Tools.Licensee Initiated Survey as Result of Ongoing Internal Assessment PNO-I-89-063, on 890721,NRC Team Insp of Allegations Re Facility Completed.Insp Dealt W/Approx 120 Concerns from Three Allegers.Preliminary Results Indicate 44 Allegations Unsubstantiated & 19 Not within Charter of Insp Team1989-07-26026 July 1989 PNO-I-89-063:on 890721,NRC Team Insp of Allegations Re Facility Completed.Insp Dealt W/Approx 120 Concerns from Three Allegers.Preliminary Results Indicate 44 Allegations Unsubstantiated & 19 Not within Charter of Insp Team PNO-I-89-039, on 890527,unidentified RCS Leakage Exceeded 2.5 Gpm & Plant Shutdown Initiated.Rcs Pressure Increased to 46 Gpm.Containment Entry Planned on 890530,after Deinerting. Maint Team Insp Initiated1989-05-30030 May 1989 PNO-I-89-039:on 890527,unidentified RCS Leakage Exceeded 2.5 Gpm & Plant Shutdown Initiated.Rcs Pressure Increased to 46 Gpm.Containment Entry Planned on 890530,after Deinerting. Maint Team Insp Initiated PNO-I-89-028, on 890411,shutdown Initiated from Full Power When RCS Unidentified Leak Rate Reached 1.5 Gpm.Charging Flow Control Valves Closed to Limit Amount of Boron Injected.Caused by Crack on Leakage Monitoring Valve1989-04-13013 April 1989 PNO-I-89-028:on 890411,shutdown Initiated from Full Power When RCS Unidentified Leak Rate Reached 1.5 Gpm.Charging Flow Control Valves Closed to Limit Amount of Boron Injected.Caused by Crack on Leakage Monitoring Valve PNO-I-88-118, on 881113,licensee Shutdown Plant in Response to High Unidentified Leakage Into Primary Containment.Caused by Increase in Unidentified Drywell Leakage.Licensee Will Replace Topwork for Both D & E Safety Relief Valves1988-11-14014 November 1988 PNO-I-88-118:on 881113,licensee Shutdown Plant in Response to High Unidentified Leakage Into Primary Containment.Caused by Increase in Unidentified Drywell Leakage.Licensee Will Replace Topwork for Both D & E Safety Relief Valves PNO-I-88-111, on 881022,manual Reactor/Turbine Trip Was Initiated Due to Lowering Main Condenser Vacuum.High Suction Differential Pressure Conditions Caused by Seaweed Impingement.All MSIVs Were Closed1988-10-24024 October 1988 PNO-I-88-111:on 881022,manual Reactor/Turbine Trip Was Initiated Due to Lowering Main Condenser Vacuum.High Suction Differential Pressure Conditions Caused by Seaweed Impingement.All MSIVs Were Closed PNO-I-88-101, on 881005,MSIV C Closed Fully During Partial Stoke Testing of Valve,Causing Water Level Decrease in Steam Generator C & Reactor Trip on lo-lo Steam Generator Level. Shutdown Extended to Perform Maint on Valve1988-10-0606 October 1988 PNO-I-88-101:on 881005,MSIV C Closed Fully During Partial Stoke Testing of Valve,Causing Water Level Decrease in Steam Generator C & Reactor Trip on lo-lo Steam Generator Level. Shutdown Extended to Perform Maint on Valve PNO-I-88-060, on 880607,while at 100% Power,Cedm 23 Dropped Into Core.Licensee Investigation Found CEDM 23 Breaker Had Tripped on Overcurrent & Upper Gripper Coil Had Electrical Short.Plant Shut Down for Estimated 4 Days for Repair1988-06-0707 June 1988 PNO-I-88-060:on 880607,while at 100% Power,Cedm 23 Dropped Into Core.Licensee Investigation Found CEDM 23 Breaker Had Tripped on Overcurrent & Upper Gripper Coil Had Electrical Short.Plant Shut Down for Estimated 4 Days for Repair PNO-I-88-049, on 880506,plant Shutdown Commenced to Locate Source of Boric Acid Buildup on Control Element Drive Mechanism Coolers & Ventilation Shroud & Unidentified Leakage.Util Plans to Replace Reactor Vessel Head O-rings1988-05-0909 May 1988 PNO-I-88-049:on 880506,plant Shutdown Commenced to Locate Source of Boric Acid Buildup on Control Element Drive Mechanism Coolers & Ventilation Shroud & Unidentified Leakage.Util Plans to Replace Reactor Vessel Head O-rings PNO-I-88-041, on 880414,unidentified Leak Exceeded 6 Gpm Limit.Leak Identified from PORV Block Valve Packing Leakoff Line.Manual Valve in Leakoff Line Shut Off.Checks for Leaks & High Temp Investigation Continuing1988-04-15015 April 1988 PNO-I-88-041:on 880414,unidentified Leak Exceeded 6 Gpm Limit.Leak Identified from PORV Block Valve Packing Leakoff Line.Manual Valve in Leakoff Line Shut Off.Checks for Leaks & High Temp Investigation Continuing PNO-I-87-052, on 870605,reactor Trip Occurred Due to Closure of All Four Msivs.Caused by Loss of One of Two Safeguards Electrical Buses.On 870606,MSIV a Failed Part Stroke Testing.Reactor in Cold Shutdown for MSIV Repair1987-06-0808 June 1987 PNO-I-87-052:on 870605,reactor Trip Occurred Due to Closure of All Four Msivs.Caused by Loss of One of Two Safeguards Electrical Buses.On 870606,MSIV a Failed Part Stroke Testing.Reactor in Cold Shutdown for MSIV Repair PNO-I-87-043, on 870514,during Reactor Trip Breaker Response Time Testing,Reactor Trip Occurred.Steam Generator Feedwater Isolation Pressure Transient Resulted in Failure of Two Lines to Thermal Relief Valves.Cause Under Investigation1987-05-15015 May 1987 PNO-I-87-043:on 870514,during Reactor Trip Breaker Response Time Testing,Reactor Trip Occurred.Steam Generator Feedwater Isolation Pressure Transient Resulted in Failure of Two Lines to Thermal Relief Valves.Cause Under Investigation PNO-I-87-037, on 870425,util Employee Arrested Offsite for Possession of Coccaine W/Intent to Sell.Employee Authorization to Enter Vital Areas Terminated 1 H After Arrest1987-04-27027 April 1987 PNO-I-87-037:on 870425,util Employee Arrested Offsite for Possession of Coccaine W/Intent to Sell.Employee Authorization to Enter Vital Areas Terminated 1 H After Arrest PNO-I-87-007, on 870129,licensee Began Normal Shutdown of Facility to Repair Leak in Steam Generator SG-1.Leak Caused by Tube Defect.Plant Will Remain Shut Down for 17 to 18 Days.State of CT Informed1987-01-30030 January 1987 PNO-I-87-007:on 870129,licensee Began Normal Shutdown of Facility to Repair Leak in Steam Generator SG-1.Leak Caused by Tube Defect.Plant Will Remain Shut Down for 17 to 18 Days.State of CT Informed PNO-I-86-095, on 861130,unit Scrammed from 100% Power Due to Malfunction of Main Transformer,Loss of Generator Load & Turbine Overspeed.Transformer Disassembly in Progress to Determine Cause of Event1986-12-0101 December 1986 PNO-I-86-095:on 861130,unit Scrammed from 100% Power Due to Malfunction of Main Transformer,Loss of Generator Load & Turbine Overspeed.Transformer Disassembly in Progress to Determine Cause of Event ML20213G4721986-11-13013 November 1986 PNS-I-86-022:on 861113,handgun Detected on Employee by Metal Detector Upon Entering Site Protected Area.Gun Voluntarily Surrendered.Review of Employee Background Revealed Nothing Unfavorable PNO-I-86-064, on 860812,reactor Tripped Due to Low Pressure Output of Steam Generator Feedwater Pump gear-driven Pump. Investigation Underway1986-08-13013 August 1986 PNO-I-86-064:on 860812,reactor Tripped Due to Low Pressure Output of Steam Generator Feedwater Pump gear-driven Pump. Investigation Underway PNO-I-86-056, on 860724 Plant Shut Down Due to Open let- Down Sys Relief Valve.While Shut Down,Reactor Tripped on Low Steam Generator Level.Caused by Level Swings Due to Malfunctioning Valve Operators1986-07-25025 July 1986 PNO-I-86-056:on 860724 Plant Shut Down Due to Open let- Down Sys Relief Valve.While Shut Down,Reactor Tripped on Low Steam Generator Level.Caused by Level Swings Due to Malfunctioning Valve Operators ML20211F8401986-06-12012 June 1986 PNS-I-86-008:on 860612,during Random Search of Contract Employee Purse at Plant Entrance,Small Bag of Marijuana Found.Employee Turned Over to Local Law Enforcement Authorities & Employment Terminated PNO-I-86-020, on 860221,controlled Shutdown Occurred Due to Sulfate Concentrations Exceeding Owners Group Guideline of 20 Parts Per Billion.Caused by Condensate Demineralizer Resin Intrusion.Plans Made to Drain & Refill Generators1986-02-24024 February 1986 PNO-I-86-020:on 860221,controlled Shutdown Occurred Due to Sulfate Concentrations Exceeding Owners Group Guideline of 20 Parts Per Billion.Caused by Condensate Demineralizer Resin Intrusion.Plans Made to Drain & Refill Generators PNO-I-86-012, on 860206,during Routine Closure Surveillance, Inboard MSIV Failed to Close.Main Steam Lines Isolated.One Inboard MSIV Remains Open.Investigation & Repair of Valve Underway1986-02-0606 February 1986 PNO-I-86-012:on 860206,during Routine Closure Surveillance, Inboard MSIV Failed to Close.Main Steam Lines Isolated.One Inboard MSIV Remains Open.Investigation & Repair of Valve Underway PNO-I-85-088, on 851121,normal 345 Kv Offsite Power Lost as Result of Personnel Error During Surveillance of Offsite Power Source Breakers.Emergency Gas Turbine Generator Failed to Start.Shutdown Capability Lost for 5 Minutes1985-11-22022 November 1985 PNO-I-85-088:on 851121,normal 345 Kv Offsite Power Lost as Result of Personnel Error During Surveillance of Offsite Power Source Breakers.Emergency Gas Turbine Generator Failed to Start.Shutdown Capability Lost for 5 Minutes ML20138R0791985-11-14014 November 1985 PNS-I-85-015:on 851113,handgun Found in Driver Attache Case of tractor-trailer Exiting Plant Protected Area.Handgun Not Discovered During Entry Search.Driver Released Under Personal Recognizance PNO-I-85-073, on 851001,unit Placed in Cold Shutdown After Ground Fault Found in Reactor Coolant Pump Motor.Pump Motor Will Be Removed to Allow Util & GE to Determine Whether Fault Accessible1985-10-0202 October 1985 PNO-I-85-073:on 851001,unit Placed in Cold Shutdown After Ground Fault Found in Reactor Coolant Pump Motor.Pump Motor Will Be Removed to Allow Util & GE to Determine Whether Fault Accessible PNO-I-85-071A, on 850927,Hurricane Gloria Located at Northampton,Ma Moving in Northeasterly Direction.Status Downgrade to Tropical Storm Expected Early Evening on 850927.Salem Unit 1 & Millstone Complex Suffered Damage1985-09-27027 September 1985 PNO-I-85-071A:on 850927,Hurricane Gloria Located at Northampton,Ma Moving in Northeasterly Direction.Status Downgrade to Tropical Storm Expected Early Evening on 850927.Salem Unit 1 & Millstone Complex Suffered Damage 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-85-058, on 850813,reactor Tripped & Main Steam Line Isolation Occurred Due to Indicated Steam Line Area High Radiation.Caused by Air Introduction Into Feedwater Sys While Placing Demineralizer in Svc1985-08-14014 August 1985 PNO-I-85-058:on 850813,reactor Tripped & Main Steam Line Isolation Occurred Due to Indicated Steam Line Area High Radiation.Caused by Air Introduction Into Feedwater Sys While Placing Demineralizer in Svc PNO-I-85-050, on 850715,reactor Tripped from Full Power When Pressure Dropped to Thermal Margin/Low Pressure Setpoint of Approx 2,130 Psi.Caused by Failure of Both Pressurizer Spray Valves to Shut1985-07-16016 July 1985 PNO-I-85-050:on 850715,reactor Tripped from Full Power When Pressure Dropped to Thermal Margin/Low Pressure Setpoint of Approx 2,130 Psi.Caused by Failure of Both Pressurizer Spray Valves to Shut ML20198B3781982-11-19019 November 1982 PNS-I-82-016:on 821119,New London,Ct Police Dept Received Bomb Threat from Male Caller Stating That Bomb Was Planted in Unit 3.Evacuation Was Initiated & All Areas Searched Resulting W/Negative Results ML20198B4831982-10-25025 October 1982 PNS-I-82-014:on 821025,Stone & Webster Telephone Operator Received Telephone Bomb Threat from Unidentified Caller Through Site Commercial Lines.Licensee Ordered Evacuation & Initiated Search.No Bomb Was Found PNO-I-82-054, on 820723,after Purging Unit 2 Containment Through Encl Bldg Filtration Sys to Unit 1 Vent Stack,Unit 2 Stack Gaseous Release Rates Exceeded Administrative Limits. Caused by Mispositioned Valve in Encl Bldg Exhaust Sys1982-07-26026 July 1982 PNO-I-82-054:on 820723,after Purging Unit 2 Containment Through Encl Bldg Filtration Sys to Unit 1 Vent Stack,Unit 2 Stack Gaseous Release Rates Exceeded Administrative Limits. Caused by Mispositioned Valve in Encl Bldg Exhaust Sys PNO-I-80-043, on 800318,one Truck Full of Chlorine Rail Tank Car Derailed at Broken Switch on Licensee Property.Car Presently Located Outside Protected Area,But Is Upright, Intact, & Stable.Formulating Plans to Replace Car on Rail1980-03-18018 March 1980 PNO-I-80-043:on 800318,one Truck Full of Chlorine Rail Tank Car Derailed at Broken Switch on Licensee Property.Car Presently Located Outside Protected Area,But Is Upright, Intact, & Stable.Formulating Plans to Replace Car on Rail ML20213D1651980-03-12012 March 1980 PNO-I-80-39:nonconservative Assumption Made in Analysis for Boron Dilution Accident Due to C-E Not Assuming RCS Water Vol Less than Total Vol of Sys.Could Cause Criticality After 10 Minutes of Rated Dilution Instead of 15 Minutes PNO-I-80-001, on 800104,isolation Condenser Isolated.Addl Insps of Containment Wall in Progress.Power Operation Will Continue Per Tech Specs for 15 Days.Precedures Require Power Be Reduced to 40% 24-h After Removing Condenser from Svc1980-01-0404 January 1980 PNO-I-80-001:on 800104,isolation Condenser Isolated.Addl Insps of Containment Wall in Progress.Power Operation Will Continue Per Tech Specs for 15 Days.Precedures Require Power Be Reduced to 40% 24-h After Removing Condenser from Svc ML20244A6191979-04-23023 April 1979 PNO-79-91:vapor Binding of Shutdown Cooling Sys Pump on 790314.Suction Restored;No Radioactive Matl Released to Environ ML20249A5891978-09-0505 September 1978 PNS-78-042:on 780903,watchman at Millstone Nuclear Power Station,Twice Attempted to Enter Protected Area W/Unloaded Pistol in Sock.After Second Incident,Watchman Ordered to Leave Site.Licensee Tested Metal Detector ML20217A0621978-08-11011 August 1978 PNO-78-143:on 780811,during Delivery of Shipment of Hydrogen,Fire Started at Delivery Truck.Fire Was Confined to Rear of Truck & Extinguished ML20216J9471978-07-17017 July 1978 PNO-78-132:on 780714,reactor Shutdown to Replace Splices in Electrical Cables Located Inside Containment at Containment Electrical Penetrations 1999-05-11 Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS MONTHYEARIR 05000245/19990081999-09-14014 September 1999
[Table view]Insp Repts 50-245/99-08,50-336/99-08 & 50-423/99-08 on 990615-0809.Four Violations Noted & Being Treated as Ncvs. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000423/19990071999-08-27027 August 1999 Insp Rept 50-423/99-07 on 990614-0715.Violations Noted & Being Treated as Ncvs.Major Areas Inspected:Review of C/A Program Using IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems IR 05000336/19990061999-07-19019 July 1999 Insp Repts 50-336/99-06 & 50-423/99-06 on 990420-0614.Ten Violations Occurred & Being Treated as non-cited Violations. Major Areas Inspected:Operations,Maint,Engineering & Plant Support IR 05000336/19982191999-06-10010 June 1999 Insp Rept 50-336/98-219 on 981214-18,990126-29,0208-19 & 0301-05.Noncited Violations Identified.Major Areas Inspected:Exam of Licensee Corrective Action Implementation IR 05000245/19990051999-06-0404 June 1999 Errata to Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05,consisting of Figure 1 ML20207G1211999-06-0303 June 1999 Insp Repts 50-245/99-05,50-336/99-05 & 50-423/99-05 on 990302-0419.No Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20207F1521999-05-25025 May 1999 Notice of Violation from Investigation Rept 1-94-021 on 940506-960329.Violation Noted:Between 740831-910407,licensee Made Changes to Facility Described in Safety Analysis Rept for Refueling Core Offloads Without Performing Evaluation ML20196K2621999-05-24024 May 1999 EN-99-020:on 980525,notice of Violation & Exercise of Enforcement Discretion Will Be Issued to Licensee.Action Based on Severity Level III Problem Consisting of Four Individual Violations Involving Refueling Outage PNO-I-99-022, on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions1999-05-11011 May 1999 PNO-I-99-022:on 990509,Millstone Unit 2 Established Reactor Criticality.Nrc Staff Providing Augmented Insp Coverage of Restart Activities,Including round-the-clock Observations of Licensee Activities During Key Operational Evolutions IR 05000336/19990031999-05-10010 May 1999 Insp Rept 50-336/99-03 on 990322-26.No Violations Noted. Major Areas Inspected:Review of Actions Taken by Util to Resolve Significant Issues List Item 21,fire Protection ML20206F4601999-04-30030 April 1999 Insp Rept 50-336/99-04 on 990315-31.Violation Noted.Major Areas Inspected:Monitored Licensee Activities During Plant Transition Between Operational Modes,Both During Normal & off-normal Working Hours PNO-I-99-016, on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve1999-04-0707 April 1999 PNO-I-99-016:on 990406,operators Initiated Plant Cooldown from Normal Operating Pressure & Temp in Mode 3,hot Standby. Cooldown Was Necessary to Minimize Further Degradation of Bonnet Pressure Seal for Valve 2-SI-652 & to Repair Valve ML20205M7201999-04-0606 April 1999 Notice of Violation from NRC OI Case 1-96-002 & Conclusions of Millstone Independent Review Team.Violation Noted. E Debarba,Deliberately Discriminated Against Supervisor in Performance Engineering Group at Millstone Station ML20205M7351999-04-0606 April 1999 Notice of Violation from Investigation in Case Numbers 1-96-002 & 1-97-007.Violation Noted:Licensee Discriminated Against Supervisor in Performance Engineering Group at Plant Due to Involvement in Protected Activities IR 05000245/19990021999-04-0202 April 1999 Insp Repts 50-245/99-02,50-336/99-02 & 50-423/99-02 on 990112-0301.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support IR 05000336/19990011999-03-29029 March 1999 Insp Rept 50-336/99-01 on 990117-0217.Violations Noted.Major Areas Inspected:Licensee C/A Program Implementation Using Guidance of NRC IP 40500, Effectiveness of Licensee Controls in Identifying,Resolving & Preventing Problems ML20205J0941999-03-12012 March 1999 Rept of Review of Millstone Units 1,2 & 3:Allegations of Discrimination in NRC Ofc of Investigations Cases 1-96-002, 1-96-007,1-97-007 & Associated Lessons Learned ML20207M1131999-03-0909 March 1999 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $88,000.Violation Noted:Employment of Two Contractor Employees Terminated in Aug 1997,in Part Because Individuals Raised Concerns Re MOV Program Manual ML20205G6161999-03-0909 March 1999 EN-99-010:on 990309,notice of Proposed Imposition of Civil Penalty in Amount of $88,000 Issued to Licensee.Action Based Upon Severity Level II Problem Involving Discrimination Against Two Contractor Employees at Millstone MOV Dept IR 05000245/19980061999-03-0101 March 1999 Insp Repts 50-245/98-06,50-336/98-06 & 50-423/98-06 on 981123-990111.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support PNO-I-99-006, on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys1999-01-29029 January 1999 PNO-I-99-006:on 990128,operators Inadvertently Reduced Spent Fuel Pool Water Level by Two Inches When Purification of Spent Fuel Pool Water Initiated.Operators Held Shift Briefing to Discuss Realigning Purification Sys IR 05000245/19982171999-01-22022 January 1999 Evaluation Repts 50-245/98-217,50-336/98-217 & 50-423/98-217 Conducted on 981026-30.Areas Evaluated:Whether NNECO Has Improved Sufficiently & Has Demonstrated Sustained Performance in Maintaining safety-conscious Work Environ PNO-I-99-004, on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review1999-01-20020 January 1999 PNO-I-99-004:on 990115,carbon Dioxide Was Inadvertently Discharged Into Unit 3 Cable Spreading Room,Containing Electrical Wiring.Ambulance Reported to Site as Precautionary Measure.Licensee Assembled Event Review IR 05000336/19980051999-01-0707 January 1999 Insp Repts 50-336/98-05 & 50-423/98-05 on 981006-1123. Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support ML20199C6381999-01-0707 January 1999 Notice of Violation from Insp on 981006-1123.Violation Noted:On or Before 981120,conduit 9-15,in Fire Area A-24,not Sealed & Tested in Accordance with Astme E-119,fire Endurance Test PNO-I-99-001, on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power1999-01-0404 January 1999 PNO-I-99-001:on 981231,Millstone Unit 2 Began Reloading Fuel Into Reactor After Extended Shutdown.Millstone Unit 3 Went Critical on 981230,after Forced Outage Due to Inadvertent MSIV Closure During Surveillance Testing at Power PNO-I-98-062, on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch1998-12-15015 December 1998 PNO-I-98-062:on 981211,Millstone Unit 3 Tripped from 100% Reactor Power During MSIV Partial Stroke Testing.Solenoid Valve Integral to MSIV Failed to Reopen When Licensed Operator Released Test Switch ML20195H6901998-11-18018 November 1998 Notice of Violation from Insp on 980818-1005.Violation Noted:Engineering Evaluations Not Performed When RCS Heatup Rate Limit Exceeded on 951217 & When RCS Cooldown Rate Limit Exceeded on Three occasions,940424,0728 & 951215 IR 05000245/19982161998-11-18018 November 1998 Insp Repts 50-245/98-216,50-336/98-216 & 50-423/98-216 on 980818-1005.Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000336/19982031998-11-0505 November 1998 Insp Rept 50-336/98-203 on 980824-0904.No Violations Noted. Major Areas Inspected:Effectiveness of Configuration Mgt Plan ML20155B1521998-10-23023 October 1998 Notice of Violation from Insp on 980810-0903.Violation Noted:Design Basis,As Described in FSAR Chapter 14,Accident Analyses Had Not Been Correctly Translated Into Plant Procedures & Acceptance Criteria IR 05000336/19982131998-10-23023 October 1998 Insp Rept 50-336/98-213 on 980810-0903.Violations Noted. Major Areas Inspected:Certain Aspects of Accident Mitigation Sys IR 05000245/19982151998-10-14014 October 1998 Evaluation Repts 50-245/98-215,50-336/98-215 & 50-423/98-215 on 980824-28.Major Areas Evaluated:Whether Licensee Has Improved Sufficiently & Has Demonstrated Sustained Performance in Maintaining safety-conscious Work Environ IR 05000336/19980041998-10-0101 October 1998 Insp Rept 50-336/98-04 on 980914-18.No Violations Noted. Major Areas Inspected:Mov Program Associated with GL 89-10 IR 05000245/19982121998-09-25025 September 1998 Insp Repts 50-245/98-212,50-336/98-212 & 50-423/98-212 on 980630-0817.No Violations Noted.Major Areas Inspected: Operations,Maintenance,Engineering & Plant Support IR 05000423/19982111998-09-11011 September 1998 Insp Rept 50-423/98-211 on 980413-24,0511-15,27-29,0609-11 & 23-25.Violation Noted.Major Areas Inspected:Evaluation of Licensee C/As & Other ICAVP Process Activities ML20154D1151998-09-11011 September 1998 Notice of Violation from Insp on 980413-24-0511-15,27-29, 0609-11 & 23-25.Violation Noted:Program Implemented TS 6.8.4.a,failed to Include Provisions to Reduce Leakage from RSS Heat Exchangers to SW Sys IR 05000424/19980061998-09-10010 September 1998 Insp Repts 50-424/98-06 & 50-425/98-06 on 980628-0815.No Violations Noted.Major Areas Inspected:Aspects of Licensee Operations,Engineering,Maint & Plant Support PNO-I-98-039, 980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 9808111998-08-12012 August 1998 PNO-I-98-039:980812,Millstone Unit 3 Was Shutdown to Repair Small Leak on Afws Discharge Noted.Current Leakage Does Not Exceed Regulatory Requirements & Shutdown Not Required by Tech Specs.Licensee Issued Press Release on 980811 ML20237D3041998-08-12012 August 1998 Notice of Violation from Insp on 980413-0508.Violations Noted:Two Examples Identified Where Licensee Not Performing Leakage Testing of safety-related Valves in Sys That Could Contain Highly Radioactive Fluids During Accident IR 05000245/19982081998-08-12012 August 1998 Insp Repts 50-245/98-208,50-336/98-208 & 50-423/98-208 on 980428-0629.Violations Noted.Major Areas Inspected: Operations,Maint,Engineering & Plant Support ML20237B0741998-08-12012 August 1998 Notice of Violation from Insp on 980428-0629.Violation Noted:Licensee Failed to Direct Test Personnel to Close & Lock RHR Outboard Drain Valve IR 05000336/19982011998-08-12012 August 1998 Insp Rept 50-336/98-201 on 980413-0508.Violations Noted. Major Areas Inspected:Licensee Ability to Identify & Resolve Deficiencies Focusing,But Not Limited To,Period of CMP Implementation & ICAVP at Parsons Power Group,Inc PNO-I-98-026, on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release1998-07-0101 July 1998 PNO-I-98-026:on 980701,Millstone Unit 3 Criticality Update Made.Nrc Staff Continues to Provide Augmented Insp of Unit 3 Restart Activities,Including round-the-clock Coverage of Key Operational.Licensee Plans No Press Release PNO-I-98-025, on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting1998-06-30030 June 1998 PNO-I-98-025:on 980630,unit 3 Established Reactor Criticality,However Reactor Was Shut Down When Control Room Operator Noticed Spiking Intermediate Range Monitor.Licensee Troubleshooting IR 05000245/19982071998-06-19019 June 1998 Insp Repts 50-245/98-207,50-336/98-207 & 50-423/98-207 on 980301-0427.Violations Noted.Major Areas Inspected:Maint, Operations,Engineering & Plant Support ML20249C6931998-06-19019 June 1998 Notice of Violations from Combined Insp on 980301-0427. Violations Noted:Prior to 980424,instrument Min Accuracy of Wind Speed Channels Were Not Measured as Required by Table 3.3-8 of Unit 2 TS 3/4.3.3.4 IR 05000423/19970831998-06-12012 June 1998 Insp Rept 50-423/97-83 on 980413-24.Violations Noted. Major Areas Inspected:Readiness of Plant Hardware,Staff & Mgt Programs to Support Safe Restart & Continued Operation of Plant Unit 3 ML20249B0421998-06-12012 June 1998 Notice of Violations from Insp on 980413-24.Violations Noted:Only 1 RCS Loop Operable W/Plant in Mode 4 on 980407 IR 05000423/19970821998-06-11011 June 1998 Insp Rept 50-423/97-82 on 980209-20.Violations Noted.Major Areas Inspected:Corrective Actions Processes 1999-09-14 |
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PRELIMINARY NOTIFICATIC'* L&ft July 7, 1977 C 08gg PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PH M This prelitninary notification constitutes EARLY notice of an 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. ,
Facil ity: Northeast Nuclear Energy Company
- Millstone Point Unit 2 Waterford, Connecticut (DN50-336) -
~
Subject:
NONCONSERVATIVE ERROR IN ANALYSIS FOR SMALL BREAK LOSS OF COOLANT ACCIDENT By letter dated June 15, 1977, the Nuclear Steam System Supolier (NSSS) notified the licensee of a nonconservative error in the anQsis for a small break loss of coolant accident (LOCA). Although a re-analysis has not yet been performed it is estimated by the NSSS and the licensee that the peak' fuel element clad temperature could increase by about 370'F, but would still be less than 2000 F following the LOCA. (10CFR50.46 limit is 2200 F).
The error was caused by improper inputs to the computer code for fuel peak linear heat generation rate (6% low) and high pressure safety in-jection (HPSI) flow rate (12% low). Combustion Engineering general plant inputs as opposed to plant specific inputs were utilized.
A similar error was made for the Fort' Calhoun facility (10% low on peak heat generation rate and 1~0% low on HPSI flow). This case has been re-
, ' analyzed with a resultant 372*F increase in peak fuel eler ent clad -
temperature. (Final value less than 2000 F)
Millstone Point Unit 2 is currently shut down to correct a main station transformer problem, (ReferencePNO-77-118) This small break analytical error will be resolved between the licensee and NRC prior to plant restart.
Mer'ia interest is expected because of close attention given to safety analyses related to nuclear power plants. The State of Connecticut has been informed. A press release is not planned by the licensee.
NRC, Region I, (Philadelphia) received notification of this occurrence by telephone from the Acting Unit Superintendent at 3:00 p.m., July 6, 1977. ,,
Contact,: GKlingler, IE x27451 FNolan, IE x27451 JSniezek, IE x27451 Distribution: TransmittedHSt/(: L3 Commissioner Kennedy C. C. Kammerer, CA G. F. Murphy, JCAE Commissioner Gilinsky S. J. Chilk, SECY 'H. H. Whiteside, SCNR
- H. R. Myers,.HCEE Transmitted: MNBBgjiM P Bldg /l', d SS Bldg ff;1 P L. V. Gossick, EDO E. G. Case, NRR C. V. Smith, NMSS S. H. Hanauer, EDO J. A. Harris, PA W. G. Mcdonald, MIPC Luge (MAIL) E. Volgenau, IE R. G. Ryan, OSP T. J. McTiernan, OIA Region s (fj l O H. K. Shapar ELD PRELIMINAR% NOTIFICATION 4-3070 9909170201 770707 D2"~t l PDR I&E '
PNO-77-123 PDR
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