Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARBECO-LTR-92-069, Special Rept:On 920601,fire Water Supply Sys Diesel Fire Pump Declared Inoperable for Maint.Caused by Failure of Manifold.Replacement Manifold Repaired & Pump Declared Operable on 9206161992-06-30030 June 1992 Special Rept:On 920601,fire Water Supply Sys Diesel Fire Pump Declared Inoperable for Maint.Caused by Failure of Manifold.Replacement Manifold Repaired & Pump Declared Operable on 920616 BECO-92-002, Special Rept:On 911214,electric Fire Pump Declared Operable. Caused by Electrical Fault in Motor Controller.Temporary Mod Continued to Keep Electric Fire Pump Available Until New Motor Controller Procured1992-01-13013 January 1992 Special Rept:On 911214,electric Fire Pump Declared Operable. Caused by Electrical Fault in Motor Controller.Temporary Mod Continued to Keep Electric Fire Pump Available Until New Motor Controller Procured BECO-90-138, Ro:On 900902,Anchor/Darling RCIC Safety Injection Check Valve Did Not Close Completely Following Startup Attempt. Caused by Loose Shaft Key.Key Modified to Provide More Clearance from Hinge Arm & Drawing Revised1990-11-14014 November 1990 Ro:On 900902,Anchor/Darling RCIC Safety Injection Check Valve Did Not Close Completely Following Startup Attempt. Caused by Loose Shaft Key.Key Modified to Provide More Clearance from Hinge Arm & Drawing Revised BECO-90-107, Special Rept:On 900803,fire Suppression Sys Diesel Fire Pump Declared Inoperable & Could Not Be Returned to Operable Status within 7 Days.Pump Repaired & Passed Surveillance Test on 9008131990-09-0606 September 1990 Special Rept:On 900803,fire Suppression Sys Diesel Fire Pump Declared Inoperable & Could Not Be Returned to Operable Status within 7 Days.Pump Repaired & Passed Surveillance Test on 900813 BECO-90-079, Special Rept:On 900527,alarm Function of Turbine Basement Wet Pipe Sprinkler Sys Declared Inoperable for More than 14 Days.Caused by Removal of Sys Alarm Card for C-7R on Window A-1.Alarm Valve Repaired & Sys Declared Operable on 9006231990-07-0202 July 1990 Special Rept:On 900527,alarm Function of Turbine Basement Wet Pipe Sprinkler Sys Declared Inoperable for More than 14 Days.Caused by Removal of Sys Alarm Card for C-7R on Window A-1.Alarm Valve Repaired & Sys Declared Operable on 900623 BECO-89-147, Special Rept:On 890826,fire Suppression Sys Diesel Fire Pump Declared Inoperable & Could Not Be Returned to Operable Status within 7 Days.New Battery Bank Procured & Currently Undergoing Discharge Testing Prior to Installation1989-09-29029 September 1989 Special Rept:On 890826,fire Suppression Sys Diesel Fire Pump Declared Inoperable & Could Not Be Returned to Operable Status within 7 Days.New Battery Bank Procured & Currently Undergoing Discharge Testing Prior to Installation ML20195G5111988-11-15015 November 1988 Special Rept:On 881017,fire Suppression Sys Electric Fire Pump Declared Inoperable.Pump Could Not Be Returned to Operable Status within 7 Days.Cause Under Investigation. Replacement Motor Installed & Pump Declared Operable ML20236E9381987-10-26026 October 1987 Special Rept:On 870917,fire Suppression Sys Electric Fire Pump Became Inoperable.Caused by Failure of Motor Windings & Moisture in Internals.Electric Fire Pump Motor Repaired & Returned to Operable Status on 871008 BECO-86-173, Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified1986-11-12012 November 1986 Partially Withheld Security Event Rept:On 861107,HVAC Duct, Penetrating Vital Area,Removed by Contracted Craft Workers Before Notifying Security.Cause Not Stated.Security Oversight of Subj Contract Work Intensified BECO-86-171, Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released1986-11-10010 November 1986 Partially Withheld Security Event Rept:On 861106,temporary Vital Area Barrier Insp Found Barrier Could Be Breached. Barrier Modified & Compensatory Security Measures Released ML20211E0731986-09-26026 September 1986 Unplanned Operating Event Rept 85-6, Manual Reactor Trip Following MSIV Closure Due to Inadvertent Emergency Feedwater Actuation,851009 BECO-86-125, Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found1986-08-29029 August 1986 Partially Withheld Security Event Rept:On 860826,bomb Threat Received.Search Initiated.No Suspicious Objects Found ML20238E4601986-08-28028 August 1986 Partially Withheld Secrity Event Rept:On 860824,bomb Threat Received for Plants.Bomb Search Initiated.No Suspicious Objects Found ML20211K8211986-06-18018 June 1986 Special Rept:On 860521,valid Failure Occurred on Div 2 Diesel Generator During Performance of Tech Spec Surveillance 4.8.1.1.2.Caused by Failure of Jacket Water Thermostatic Control Valve to Open ML20238E4591986-06-17017 June 1986 Partially Withheld Security Event Rept:On 860612,withheld Discovery Made Re 860604 Moderate Loss of Security Effectiveness.Caused by Inadequate Post Orders & Training for Assignment.Assignments Will Be Specifically Addressed 05000000/LER-1986-009, Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised1986-04-14014 April 1986 Ro:On 860312,discovered That LER 2-86-04 & LER 86-009 Not Submitted to Nrc.Caused by Misplaced Repts.Repts Telecopied to Nrc.Procedure for Distribution of Repts Revised BECO-86-016, Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended1986-02-20020 February 1986 Partially Withheld Security Event Rept:On 860215 Security Officer Appeared to Be Asleep at Post at Vital Area Penetration.Unathorized Entry of Vital Area Did Not Occurr. Security Officer Relieved of Duty & Suspended BECO-85-220, Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured1985-12-0909 December 1985 Partially Withheld Security Event Rept:On 851204 Vertical Pipe Chase Not Locked.Lock Removed When Surveys Indicated Radiation Level Below Requirement for Locked High Radiation Level.Pipe Chase Will Be Secured ML20138M1531985-10-17017 October 1985 Ro:On 850927,employee Observed That Fuel Grapple on Refuel Floor Latched to Spent Fuel Bundle & Trolley Moved,Damaging Mast.Caused by Operator error.Two-man Rule Imposed Until Investigation Complete.Mast Will Be Repaired ML20128K9831985-07-0505 July 1985 Special Rept:On 840208,sprinkler Sys in Emergency Diesel Generator Day Tank Area Declared Inoperable When Once/Cycle Surveillance Test Failed.Caused by Inadequate Design of Sprinkler Sys Initiation Logic.Logic Modified BECO-LTR-84-113, Special Rept:On 840628,during Refueling Outage,Electric Fire Pump Failed While Conducting Yearly 0-150% Capacity Test. Caused by Shorting within Motor.Motor Rewound.Fire Pump Not Returned to Operable Status within Required 7-day Peri1984-07-26026 July 1984 Special Rept:On 840628,during Refueling Outage,Electric Fire Pump Failed While Conducting Yearly 0-150% Capacity Test. Caused by Shorting within Motor.Motor Rewound.Fire Pump Not Returned to Operable Status within Required 7-day Period BECO-84-108, Updated Special Rept:On 820118,carbon Dioxide Fire Suppression Sys in Cable Spreading Room Determined Inoperable.Carbon Dioxide Sys Main Shutoff Valve Closed & Tagged,Allowing Either Automatic or Manual Operation1984-07-16016 July 1984 Updated Special Rept:On 820118,carbon Dioxide Fire Suppression Sys in Cable Spreading Room Determined Inoperable.Carbon Dioxide Sys Main Shutoff Valve Closed & Tagged,Allowing Either Automatic or Manual Operation AECM-84-0204, Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored1984-04-0606 April 1984 Special Rept 84-017/0:on 840304,Fire Doors 1A401 & OC219 Blocked Open to Support Maint Activities.Fire Watches Established Until Doors Restored ML20198H3691983-11-14014 November 1983 Ro:On 831003,results of as-found Tests Indicated Crosby Main Steam Relief Valves Had Lift Points Exceeding Tech Spec Limits.Valves Disassembled & Rebuilt by Mfg ML20105D2431983-06-24024 June 1983 Special Rept:Five Individuals Found to Have Received Radiation in Excess of 10CFR20.101 Limits W/O Required Documentation.Caused by computer-based Sys Feature Allowing Use of Outdated Info & Personnel Error.Procedures Revised ML20137G4501981-03-24024 March 1981 Ro:During walk-through of Operator Training Program, O-ring Seal of Filter Holder Found Not Seated Properly Causing Partial Bypass of Filter for Air Sucked Into instrument.Filter-in Lock Adjusted ML20062J7421980-10-31031 October 1980 RO 80-078/01X-0:on 801030,analysis of Salt Svc Water Sys Conducted in Response to IE Bulletin 79-14 Indicated Design Deficiency.Caused by Installation of Anchor Point Outside Tornado Missile Barrier.Relocation Planned ML20071F0861980-09-25025 September 1980 Ro:On 800912,sample Analysis Taken from Hydrazine Addition Tank Indicated Sodium Chloride in Tank.Anonymous Telcon Indicated Salt May Have Been Added Prior to Labor Strike by Unknown Persons ML20136C3941979-08-16016 August 1979 RO 79-031/01X-0:on 790816,not That Auxiliary Emergency Bus Breakers May Not Open Automatically During Seismic Event. Caused by Design Error.Existing Spare Undervoltage Relays Will Be Used. Control Room Operators Reinstructed ML20136B6441979-08-0909 August 1979 RO 79-029/01X-0:on 790612,degradation of Primary Containment Integrity Occurred in Violation of Tech Specs 3.7.A.2.While Investigating,Disc in 6-inch Check Valve Was Removed, Violating Containment Integrity.Rept to Follow ML20086D5141978-01-0606 January 1978 Telecopy Ro:On 780105,discovered That One of Two Nuclear Engineering Co Model B3-1 Shipping Casks Provided w/1-inch Diameter Lid Bolts Rather than 1-1/4 Inch Size Specified in Certificate of Compliance 6058 ML20086D5201977-12-14014 December 1977 Telecopy Ro:Heating Steam Coil Leak in Reactor Bldg Ventilation Supply Unit V-AH-4A Resulted in Freezing of Condensate at Inlet to Unit & Subsequent Inoperability of Associated Secondary Containment Isolation Dampers ML20086D5371977-10-14014 October 1977 Telecopy Ro:Insp of Internal Torus Catwalk Support Structure Revealed That Catwalk Mitered Sections Not All Attached to Horizontal Catwalk Support Plates in Some Manner.Attachment Locations Will Be Upgraded ML20086D5501977-10-13013 October 1977 Telecopy Ro:On 771012,local Leak Rate Testing of MSIV AO-2-80A & Nitrogen Instrument Air Sys Isolation Valve CV-7436 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation ML20086D5541977-10-0505 October 1977 Telecopy Ro:On 771004,local Leak Rate Testing of HPCI Sys Discharge Isolation Check Valve HPCI-9 Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation ML20086D5571977-09-29029 September 1977 Telecopy Ro:On 770929,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO-14-13A Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Cause Under Investigation ML20086D5611977-09-14014 September 1977 Telecopy Ro:On 770913,local Leak Rate Testing of Core Spray Inboard Isolation Check Valve AO 14-13B Indicated That Leakage Exceeded Tech Spec Acceptance Criteria.Related Event on 770914 ML20086D5671977-09-12012 September 1977 Telecopy Ro:Main Steam Drain Isolation Valve MD 2373 & Main Steam Outboard Isolation Valve AO 2-86A Exceeded Tech Spec Acceptance Criteria for Local Leak Rate Tests ML20086D6421977-07-11011 July 1977 Telecopy Ro:On 770709,determined That Recombiner Sys a Offgas Flow Control Valve PCV 7489A Could Be Opened W/ Controlling Solenoid Valve Deenergized.Valve Held from Svc Pending Investigation ML20137G4461977-06-23023 June 1977 Ro:On 770621,radioactive Source Containing 200 Mci Cs-137 Recovered from Brine Well 33.Incident Described in ML20086F0801977-06-0606 June 1977 Ro:On 770506,plant Iodine & Particulate Release Rate Exceeded 4% of Facility Tech Spec Averaged Over Second Calendar Quarter of 1977.Caused by Fuel Perforations Coupled W/End of Cycle Testing & Reactor Coolant & Steam Leaks ML20086D6911977-03-0202 March 1977 Telecopy Ro:On 770301,torus Water Vol Found to Be Slightly Below Min Vol Established by Tech Specs.Water Vol Restored to Normal Operating Level ML20086D7031977-02-24024 February 1977 Telecopy Ro:On 770223,while Withdrawing in-sequence Control Rod to Bring Reactor Critical,Reactor Period of Less than 5 Obtained ML20086F4181976-12-0909 December 1976 RO Re Plant Iodine & Particulate Release Rate Exceeding 4% of Tech Spec 3.8.C.2 Averaged Over Fourth Calendar Quarter 1976.Caused by Leaks in Reactor Water Cleanup Sys.Leaks Repaired & Equipment Modified to Reduce Leakage ML20070J8681976-10-20020 October 1976 RO 76-13:on 760916,normal Boric Acid Makeup to Vol Control Tank Could Not Be Accomplished Due to Plugging of Chemical & Vol Control Sys Line 1-inch-CH-56-152.Cause Unknown.Line Will Be Inspected for Indications of Solidification ML20070J8581976-10-0101 October 1976 RO 76-12:on 760909,low Pressure Alarm Occurred on Safety Injection Accumulator C,Resulting in Pressure Reduction. Caused by Partially Open HCV 1936 & Body to Bonnet Leaks on HCV 1898 & 1549.Valves Repaired & Accumulator Repressurized ML20070J8961976-09-29029 September 1976 RO 76-05:on 760915,pressurizer Level Fell Below 45% Level Setpoint,Resulting in Decreases of Pressurizer Pressure & Vol Control Tank Level.Caused by Leaking Tube in Steam Generator A.Cause of Tube Failure Will Be Evaluated ML20070J8801976-09-24024 September 1976 RO 76-07:on 760913,monthly Average of Gaseous & Airborne Particulate Wastes for Previous 12 Months Found Greater than Tech Spec Limit.Caused by Interpretational Changes in Tech Spec Section 3.11.B.New Limit Approved ML20086D7881976-09-10010 September 1976 Telecopy Ro:On 760909,discovered That Torus Water Vol Several Hundred Cubic Ft Below 68,000 Cubic Ft Min Required by Tech Specs.Caused by Failure to Correct for Vol Vs Level Correlation ML20086D8231976-05-0505 May 1976 Telecopy Ro:On 760504,during Routine Surveillance Test, Primary Containment Oxygen Concentration Found to Be in Excess of Tech Spec Limit.Caused by Leakage from Drywell Instrument Air Sys Into Containment Nitrogen Supply Line 1992-06-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20212C2921999-09-16016 September 1999 SER Accepting Licensee Request for Relief from ASME Code Section XI Requirements as Endorsed by 10CFR50.55a for Containment Insp for Pilgrim Nuclear Power Station ML20216F3511999-09-0808 September 1999 ISI Summary Rept for Refuel Outage 12 at Pnps ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20209C4731999-07-0707 July 1999 Addendum to SE on Proposed Transfer of Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generation Co ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20196H2451999-06-29029 June 1999 SER Denying Licensee Proposed Alternative in Relief Request PRR-13,rev 2.Staff Determined That Proposed Alternative Provides Insufficient Info to Determine Adequacy of Scope of Implementation ML20209A8901999-06-28028 June 1999 SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209B9861999-06-23023 June 1999 Rev 13A to Pilgrim Nuclear Power Station COLR for Cycle 13 ML20217N9061999-06-21021 June 1999 Rept of Changes,Tests & Experiments for Period of 970422-990621 ML20195K3431999-06-15015 June 1999 Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water System Piping for Plant ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20207E7471999-05-27027 May 1999 Safety Evaluation Granting Request Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of HWC to License DPR-35 ML20206M1971999-05-11011 May 1999 SER Accepting Request for Approval to Repair Flaws in ASME Code Class 3 Salt Svc Water Piping at Plant ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20207J5471999-03-0909 March 1999 Training Simulator,1999 4-Yr Certification Rept ML20207F9401999-03-0101 March 1999 Long Term Program Semi-Annual Rept for Pilgrim Nuclear Power Station ML20207H5451999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Pilgrim Nuclear Power Station.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.With ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20197J3591998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Pilgrim Nuclear Power Station.With ML20195C9951998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Pilgrim Nuclear Power Station.With ML20154K0721998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Pilgrim Nuclear Power Station.With ML20153D3901998-09-22022 September 1998 Safety Evaluation Granting 970707 Request to Use Guidance in GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Pilgrim Nuclear Power Station ML20197C5011998-09-0404 September 1998 Rev 12C,Pages 4 & 5 to Pilgrim Nuclear Power Station Colr ML20197C5471998-08-31031 August 1998 Rev 12C to Pilgrim Nuclear Power Station Colr ML20151W8231998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Pilgrim Nuclear Power Station.With ML20237E2251998-08-26026 August 1998 Suppl & Revs to SE for Amend 173 for Pigrim Nuclear Power Station ML20237A9941998-07-31031 July 1998 Monthly Operating Rept for Pilgrim Nuclear Power Station ML20236U8201998-07-13013 July 1998 Rev 12B to Pilgrim Nuclear Power Station COLR (Cycle 12) ML20236P0151998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Pilgrim Nuclear Power Station ML20249A3741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Pilgrim Nuclear Power Station.W/Undated Ltr ML20247H2081998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Pilgrim Nuclear Power Station ML20207B7601998-03-31031 March 1998 Final Rept, Pilgrim Nuclear Power Station Site-Specific Offsite Radiological Emergency Preparedenss Prompt Alert & Notification System Quality Assurance Verification, Prepared for FEMA ML20216G3911998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Pilgrim Nuclear Power Station ML20216J3741998-03-19019 March 1998 Safety Evaluation Accepting Licensee Request to Evaluate Elevated Tailpipe Temp on Safety Relief Valve SRV 203-3B ML20248L2241998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Pilgrim Nuclear Station ML20202G5251998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Pilgrim Nuclear Power Station ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20203D6101997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Pilgrim Nuclear Power Station ML20202D5761997-11-0808 November 1997 1997 Evaluated Exercise BECO-LTR-97-111, Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Pilgrim Nuclear Power Station ML20217D6431997-10-0101 October 1997 Safety Evaluation Granting Request for Approval to Repair Flaws in Accordance W/Gl 90-05 for ASME Class 3 SSW Piping for Pilgrim ML20217H5621997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Pilgrim Nuclear Power Station ML20216J4131997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Pilgrim Nuclear Power Station ML20210J3321997-07-31031 July 1997 Monthly Operating Rept for Jul 1997 for Pilgrim Nuclear Power Station 1999-09-08
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