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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20086G2701976-01-0808 January 1976 AO 75-79:on 751229,local Leak Test Identified through- Leakage of B Loop RHR Torus Spray Valve MO-3-10-38B & Torus Cooling Return Valve MO-3-10-34B.Cause Under Investigation ML20086G2721976-01-0505 January 1976 AO 75-78:on 751226,drywell Radiation Monitor Inoperative. Caused by Flow Blockage in on Stream Sample Line.Sample Point Changed to Reestablish Sample Flow to Drywell Radiation Monitor ML20086G2741975-12-30030 December 1975 AO 75-76:on 751220-21,local Leak Rate Test Identified through-leakage on Loop a & B RHR Outboard Injection Valves MO-3-10-154A & B.Cause Not Determined.Inboard Isolation Valves Verified as Leaktight & Closed ML19343C2181975-12-23023 December 1975 AO 50-219/75-33:on 751212,during 6-month Load Test on Station a batteries,125 Volt Dc Distribution Ctr de-energized.Caused by Personnel Error in Following Procedure.Distribution Ctr re-energized ML20090C9991975-12-12012 December 1975 AO 75-33:on 751212,125-volt Dc Distribution Ctr of Station a Battery Inadvertently de-energized.Caused by Failure to Establish Proper Breaker Lineup Preparation for Conducting Battery Load Test.Procedure changed.W/751219 Memo ML19343C2191975-12-11011 December 1975 AO 50-219/75-32:on 751203,during Testing,Emergency Diesel Generator 1 Failed to Start When Simulated Loss of Power Condition Applied to Fast Start Logic Circuit.Caused by Failure of Relay to Operate Due to Varnish on Armature ML20086H0411975-12-0505 December 1975 AO 75-72:on 751126,core Spray 3A Full Flow Test Valve MO-3-14-26A Failed to Close.Caused by Broken Wire on Closing Torque Switch in Valve Operator.Broken Wire Repaired & Proper Valve Operator Verified ML20086F8431975-12-0505 December 1975 AO 75-77:on 751126,LS-4223 Failed to Operate RHR Head Spray Line High Point Vent SV-4223 on Low Accumulator Level.Caused by Blown Fuse in Solenoid Valve Circuit.Grounded Wire Repaired & Vent Valve Returned to Svc ML20126E8281975-12-0303 December 1975 AO 50-219/75-31:on 751124,during Operability Test of Torus to Drywell Vacuum Breakers,Alarm Sys 2 Failed to Annunciate in Control Room When V-26-4 Opened.Caused by Failure of Relay Due to Contacts Being Detective.Relay Replaced ML20086F8491975-12-0101 December 1975 Telecopy AO 75-77:on 751126,LS-4223 Failed to Operate SV-4223 on Low Accumulator Level.Caused by Blown Fuse in Solenoid Valve Circuit.Operator Manually Vented Accumulator to Ensure Head Spray Line Maintained Filled ML20086H0461975-11-26026 November 1975 Telecopy AO 75-72:on 751126,core Spray Full Flow Test Valve MO-3-14-26A Failed to Close.Caused by Broken Wire on Closing Torque Switch in Valve Operator.Broken Wire Repaired & Proper Valve Operation Verified ML20086F8551975-11-26026 November 1975 AO 75-76:on 751117,rigid Pipe Support Found Broken on RHR Shutdown Cooling Suction Line.Caused by Component Failure. Pipe Support Replaced.Investigation Continuing ML20086F8711975-11-26026 November 1975 AO 75-75:on 751117,reservoirs of Two Hydraulic Snubbers Found Empty.Caused by Leaking O-rings & Gaskets.Defective gaskets,seals,O-rings & Fittings Will Be Replaced & Snubbers Will Be Checked ML20086F8801975-11-26026 November 1975 AO 75-74:on 751116,setpoint of RCIC Steam Supply Line Area High Temp Switch TE-TS 4939A Found Less Conservative than Specified by Tech Specs.Caused by Slight Setpoint Drift. Switch Recalibr,Tested & Returned to Svc ML20090D0071975-11-25025 November 1975 AO 75-31:on 751124,drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-4 Opened. Caused by Component Failure.Corrective Action Under Investigation ML20086F8961975-11-21021 November 1975 AO 75-73:on 751113,leak Observed on RHR Sys Relief Valve RV-35B.Caused by Throttling of MO-2-10-154B Valve Resulting in Crack.Weld Repairs Will Be Made to Relief Valve in Accordance W/Approved Procedures ML20086F8611975-11-18018 November 1975 Telecopy AO 75-76:on 751117,rigid Pipe Support Found Broken on RHR Shutdown Cooling Suction Line.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086F8741975-11-18018 November 1975 Telecopy AO 75-75:on 751117,two Outside Drywell Snubbers Found to Have Empty Reservoirs.Cause Under Investigation. Corrective Action to Be Determined After Investigation ML20086F9061975-11-17017 November 1975 AO 75-71:on 751107,cracked Weld on 1-inch Line to Relief Valve RV-35B Observed.Caused by Throttling MO-2-10-154B Resulting in Cracked Weld.Repairs Completed in Accordance W/Approved Procedure ML20086F8901975-11-17017 November 1975 Telecopy AO 75-74:on 751116,setpoint of RCIC Steam Supply Line High Temp Switch TE-TS 4939A Found Less Conservative than Allowed by Tech Specs.Caused by Slight Setpoint Drift. Switch Recalibr & Returned to Svc ML20086F9181975-11-14014 November 1975 AO 75-70:on 751104,reservoirs of Five Hydraulic Snubbers Found Empty.Caused by Leaking O-rings & Gaskets.Defective Gaskets & O-rings Will Be Replaced ML20086F9021975-11-14014 November 1975 Telecopy AO 75-73:on 751113,leak on Body of RV-35B RHR Sys Relief Valve Observed.Caused by Throttling of MO-2-10-154B Valve Resulting in Crack.Rhr Loop B Shut Down in Preparation for Repair of Relief Valve ML20086F9111975-11-10010 November 1975 Telecopy AO 75-71:on 751107,cracked Weld on Line to RV-35B Observed.Caused by Throttling Down on MO-2-10-154B Resulting in Weld Crack.Repairs Completed.Pipe Vibration Readings Taken to Determine If Mods Required ML20086H0521975-11-0707 November 1975 AO 75-71:on 751030,drywell Oxygen Analyzer Sample Sys Outer Isolation Valve SV-3978B Failed.Caused by Dirt on Seat & in Body of Valve.Valve Internals & Seat Cleaned.Valve Disc, Piston Rings & Bonnet O-ring Replaced ML20090D0161975-11-0707 November 1975 AO 75-30:on 751106,low Reactor Pressure Core Spray Valve Permissive Pressure Switches Re 17 a & C Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability.Pressure Switches Recalibr ML20090D0601975-11-0606 November 1975 AO 75-29:on 751027,torus Drywell Vacuum Breakers Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened. Caused by Sticking Microswitch ML20086F9231975-11-0505 November 1975 Telecopy AO 75-70:on 751104,reservoirs of Five Hydraulic Snubbers Found Empty.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086H0621975-11-0303 November 1975 AO 75-70:on 751024,drywell Purge Supply Isolation Valve A0-3520 Operated W/O Manual Initiation.Caused by Incorrect Implementation of Mod.Piping Corrected & Will Be Monitored ML20086H0751975-10-31031 October 1975 AO 75-68:on 751021,torus Makeup Supply Isolation Valve AO-3523 Found to Leak in Excess of 2,000 Cc/Minute.Caused by Closing Spring Not Providing Sufficient Force to Fully Close Valve.Closing Spring Adjusted ML20086H0851975-10-31031 October 1975 AO 75-67:on 751021,torus Makeup Supply Isolation Check Valve 276Y Found Leaking in Excess of 2,000 Cc/Minute.Caused by Valve Piston Being Hung Up During Operation.Check Valve Repaired & Local Rate Test Repeated ML20086H0561975-10-31031 October 1975 Telecopy AO 75-71:on 751030,isolation Valve SV 3978B Failed. Cause Under Investigation.Corrective Action to Be Determined ML20086F9381975-10-31031 October 1975 AO 75-68:on 751021,O-ring Gasket Leak Discovered on Torus Purge Supply Valve AO-2521B.Caused by Use of Improper Connection for Testing Double O-ring Seal.Connection Capped & Leak Checked Successfully ML20086F9291975-10-31031 October 1975 AO 75-69:on 751021,nitrogen Found to Leak Out of Test Connection on Inboard Flange of AO-2519.Caused by Use of Wrong Connection for Testing Double O-ring Seal.Connection Capped & Leak Checked Successfully ML20086F9521975-10-30030 October 1975 AO 75-66:on 751020,APRM B Flow Bias Signal Failed Upscale. Caused by Internal Ground in Channel Flow Transmitter D Combined W/Installed Instrument Loop Ground,Lowering Total Loop Resistance.Defective Components Replaced ML20090D0761975-10-28028 October 1975 AO 75-29:on 751027,torus to Drywell Vacuum Breaker Alarm Sys II Failed to Annunciate When Vacuum Breaker V-26-8 Opened.Caused by Component Failure.Corrective Action Under Investigation ML20086H0741975-10-24024 October 1975 Telecopy AO 75-69:on 751023,O-ring Gasket Leak Found on Drywell Purge Supply Valve AO-3505.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086H0681975-10-24024 October 1975 Telecopy AO 75-70:on 751024,drywell Purge Supply Isolation Valve AO-3520 Operated W/O Manual Initiation.Caused by Incorrect Implementation of Mod.Valve Failed Closed & Will Be Repaired ML20086F9661975-10-24024 October 1975 AO 75-65:on 751015,setpoints on Reactor High Pressure Scram Switches Found Less Conservative than Specified by Tech Specs.Caused by Instrument Setpoint Shift.Channel D Switch Recalibr,Tested & Returned to Svc ML20090D0941975-10-24024 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil Replaced ML20086H0901975-10-21021 October 1975 Telecopy AO 75-67:on 751021,torus Makeup Supply Isolation Check Valve 276Y Found Leaking in Excess of 2,000 Cc/Minute. Cause Under Investigation.Corrective Actions to Be Determined After Investigation ML20086H0811975-10-21021 October 1975 Telecopy AO 75-68:on 751021,torus Makeup Sys Isolation Valve AO-3523 Found to Leak in Excess of 2,000 Cc/Minute.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086F9581975-10-21021 October 1975 Telecopy AO 75-66:on 751020,logic Aprm/Rbm B Flow Bias Signal from FT-2-2-110D Failed Upscale.Caused by Failure of Second Ground on Recirculation Drive Flow Transmitter Signal Loop.Flow Signal Corrected ML20086F9441975-10-21021 October 1975 Telecopy AO 75-68:on 751021,leak Found on O-ring Gasket on Torus Purge Supply Valve AO 2521A.Cause Under Investigation. Corrective Action to Be Determined After Investigation ML20086F9491975-10-21021 October 1975 Telecopy AO 75-67:on 751021,diesel Generator Breaker E-4 Inoperable.Caused by Inoperative Charging Motor Failing Due to Brush Wear.Breaker Replaced ML20086F9331975-10-21021 October 1975 Telecopy AO 75-69:on 751021,O-ring Gasket Leak Discovered on Drywell & Torus Inerting Nitrogen Supply Valve AO-2519.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20090D1141975-10-17017 October 1975 AO 75-27:on 751008,low Reactor Pressure Core Spray Valve Permissive Pressure Switches RE17B & D Tripped at Pressure Less than Min Required Value.Caused by Switch Repeatability. Pressure Switches Recalibr ML20090D1041975-10-16016 October 1975 AO 75-28:on 751015,standby Gas Treatment Sys 1 Inoperable. Caused by Air Solenoid Valve Coil Failure.Defective Solenoid Coil replaced.W/751016 ML20086F9701975-10-16016 October 1975 Telecopy AO 75-65:on 751015,setpoint on Reactor High Pressure Scram Switches Found to Be Less Conservative than Specified by Tech Specs.Caused by Instrument Setpoint Shift. Channel D Switch Recalibr,Tested & Returned to Svc ML20086H0961975-10-16016 October 1975 AO 75-66:on 751006,RCIC Inboard Steam Supply Isolation Valve MO-3-13-15 Failed to Close.Cause Not Identified.Valve Stroked Successfully.Failure Not Repeatable ML20086H1061975-10-10010 October 1975 AO 75-65:on 751002,drywell Radiation Monitor Inoperable. Caused by Rust Blockage of Pressure Control Valve.Valve Cleaned,Reassembled & Returned to Svc 1976-01-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217K4451999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Oyster Creek Nuclear Generating Station.With ML20217E3021999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pilgrim Nuclear Station.With ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 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 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211P6731999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Oyster Creek Nuclear Generating Station.With ML20216E6881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pilgrim Nuclear Power Station.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20210R3401999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Pilgrim Nuclear Power Station.With ML20211A7051999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Oyster Creek Nuclear 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 ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20209E6191999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Pilgrim Nuclear Power Station.With ML20209G0631999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Oyster Creek Nuclear Generating 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 ML20212H5491999-06-18018 June 1999 Non-proprietary Rev 4 to HI-981983, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool 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 ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20195G8231999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Pnps.With ML20195E7961999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Oyster Creek Nuclear Generating Station.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 ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206J6611999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Pilgrim Nuclear Power Station.With ML20206N7431999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Oyster Creek Nuclear Generating Station.With ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5401999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Oyster Creek Nuclear Generating Station.With ML20205L0221999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Pilgrim Nuclear Power Station.With ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.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 ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20204C8201999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Oyster Creek Nuclear Generating Station.With 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 ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20195E8321998-12-31031 December 1998 10CFR50.59(b) Rept of Changes to Oyster Creek Sys & Procedures, for Period of June 1997 to Dec 1998.With ML20199E4671998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Oyster Creek Nuclear Generating Station.With 1999-09-08
[Table view] |
Text
q O O l PHILADELPHIA ELECTRIC COMPANY !
l l 2301 MARKET STREET l -
PHILADELPHIA. PA.19101 i
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12153841 4000 .
I October 14, 1974
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Mr. A. Giambusso ,
Deputy Director of Reactor Projects ,
United States Atomic Energy Conmission %..fi./ S ,3 Directorate of Licensing *. ' ;3 Washington, D.C. 20545 ".; /[ " ;
'I .-
Dear Mr. Giambusso:
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Subject:
Abnormal Occurrence . -. g N' The following occurrence was reported to Mr. Walt Baunack, A.E.C. Region 1 Regulatory Operations Office on October'4, 1974.
Written notification was made to Mr. James P. O'Reilly, Region 1 Regulatory Operations Office on October 4, 1974. In accordance with Section 6.7.2.A of the Technical Specifications, Appendix A of DPR-56 for Unit 3 Peach Botton Atomic Power Station, the following report is being submitted to the Directorate of Licensing as an Abnormal Occurrence:
Reference:
License Number DPR-56 Technical Specification References 3.5.D.1, 3.5.D.2, 3.7.D.2., plus Tablu 3.7.1 Report No.: 50-278-74-11 Report Date: October 14, 1974 Occurrence Date: October 4, 1974 Facility: Peach Bottom Atomic Power Station R.D. 1, Delta, Pennsylvania 17314 Identification of Occurrence:
RCIC steam line drain valve failure to close.
Conditions Prior to Occurrence:
Reactor was operating at approximately 1% power with primary coolant pressure of-150 psig. RCIC operability testing in progress.
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Mr. A. Giambusso October 14, 1974 fx Page 2 O- u Description of Occurrence: .
During surveillance testing of the RCIC system during a plant startup, the inner RCIC steam line drain valve ( AO-3-13 -34 )
failed to close.
Desionation of Apnarent Cause of Orcurrence:
A piece of wold slag had entered the valve and became wedged in the below seat stem guide, preventing the valve from closing.
Analysis of Occurrence:
The RCIC main steam line drain system is equipped with a drain pot, a steam trap and two air operated isolation. valves in series. Water which condenses in the main steam line is passed through two air operated isolation valves in series to the main condenser. Both of these isolation valves close automatically on RCIC initiation. Since only one valve was affected by this occurrence, system operability was not affected.
Corrective Action:
After removing the RCIC system from service and initiating the required surveillance tests , the valve was disassembled and thoroughly cleaned. The disc and seat were machined to remove indentations caused by the foreign object and then lapped. The valve was reassembled, leak tested and returned to service.
Failure Data:
No previous failures of this type have occurred.
Very truly yours,
/}[,/ /
M./.[Goney[gr y Let [~
y Asd't Gen'l Superintendent Generation Division cc: Mr. J. P. O'Reilly Director Region 1 United States Atomic Energy Commission 631 Park Avenue King of Prussia, PA 19406 L
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