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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 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 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 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 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 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 ML20085G9661973-12-22022 December 1973 RO 50-293/73-21:on 731203,HPCI Inverter Failed.Caused by Increasing Dc Battery Sys a Voltage to 140 Volts.Station Personnel Advised Against Increasing Voltage Above 135 Volts & Caution Tags Placed on Battery Chargers ML20206K7091972-11-0202 November 1972 Unusual Occurrence UO-72-6:on 720924 & 29,out-of-svc Condition of Primary Sys Boundary Coolant Leakage Air Sampling Sys Occurred.Caused by Moisture Accumulating in Detection Equipment.Mod to Equipment Designed 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 ML20196E2151998-12-31031 December 1998 1998 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept.With ML20206Q2741998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Pilgrim Nuclear Power Station.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 ML20236M8511997-12-31031 December 1997 1997 Annual Rept for Boston Edison & Securities & Exchange Commission Form 10-K Rept ML20198L7701997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Pilgrim Nuclear Power Station 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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l-l BOSTON EDISON Pilgrirn Nuclear Power station Rocky Hill Road Plymouth, Massachusetts 0236o Ralph G. Bird sencr Vice President - Nuclear November 15, 1988 BECo Ltr. #88 156 U.S. Nuclear Regulatory Commission Docket No: 50-293 Document Control Desk License No: DPR-35 Hashint in, DC 20555
SUBJECT:
Special Report . inoperable Electric Fire Pump
Dear Sir:
This special report is being submitted in accordance with Pilgrim Nuclear Power Station Technical Specification 3,12.B.a. The report is required because the Fire Suppression System Electric Fire Pump (EFP) was declared inoperable on October 17, 1988 at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> and could not be returned to operable status within seven days. The EFP was declared inoperable when metal shavings were fou"d in the motor bearing grease during a preventive maintenance inspection. Refer to Attachment I for further details.
During the period that the EFP was inoperable, the plant was in the cold shutdown condition, and the reactor vessel head was installed. The Diesel l
Fire Pump was in standby and capable of autostart and function. The EFP motor was replaced and returned to operable status on November 10, 1988.
Please do not hesitate to contact me if you have any questions regarding this subject.
hah R. G. Bird JLK/bal r]!k s e m m- < \
7-U.S. Nuclear. Regulatory Commission Docket No:'50-293 License No: DPR-35 Page 2 cc: Mr. Hilliam T. Russell Regional Administrator, Region I U.S. Nuclear Regulatcry Commission 475 Allendale Road King of Prussia, PA 19a06 Mr. D.G. Mcdonald, Project Manager Division of Reactor Projects I/II Office of Nuc1 car Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop: 14D1 One White Flint North 11555 Rockville Pike Rockville, MD 20852 Senior NRC Resident Inspector Pilgrim Nuclear Power Station 4
f
ATTACHMENT I Boston Edison Company Docket No. 50-293 Pilgrim Nuclear Power Station License No. DPR-35 The water supply to the Fire Suppression System is delivered by either the F.FP or the diesel driven fire pump (DFP). Tne DFP is redundant to the EFP and is available for standby and emergency use (loss of AC power). The EFP and DFP are each rated at 2,000 gallons per minute and discharge to the 12" Fire Suppression System header.
The EFP was declared inoperable on October 17, 1988 at 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> following the discovery of metal shavings in the motor bearing grease. The discovery was made during a preventive maintenance inspection being performed under Mainter,ance Request 88-33-283. Failure and Halfunction Report 88-273 was written to document the problem.
During the period that the EFP was inoperable, the DFP surveillance was verified to be current and the DFP was in standby and capable of autostart and function. Further, the Pilgrim Station Fire Truck was off-site for preventive maintenance. The maintenance facility was contacted and notified of the potential need for the fire truck on short notice. The truck was maintained
", in a ready-to-drive state, approximately one hour from Pilgrim if needed.
Additional precautions included postponement of certain surveillances that required starting of the diesel fire pump to avoid risks to the equipment should it be required for an emergency in the absence of the EFP. These measures are consistent with Procedure Number 2.5.54, "Loss of All Fire Suppression Pumps or Loss of Redundancy in the Fire Water Supply System". The procedure outlines immediate and subsequent operator actions that include measures to be taken when a loss in redundancy of the Fire Suppression System pumps occurs. The measures are commensurate with the degree of loss of redundancy and are determined by the Hatch Engineer in consultation with the Fire Protection and Prevention Officer (FPPO) or designee.
Tho cause of the metal shavings is currently under investigation. A replacement motor for the EFP was installed and the pump declared operable on November 10, 1988.
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