ML20086J030
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| ML20086J030 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 03/24/1975 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20086J021 | List: |
| References | |
| AO-75-21, NUDOCS 8401230050 | |
| Download: ML20086J030 (1) | |
Similar Documents at Peach Bottom | |
|---|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20086G2701976-01-0808 January 1976
[Table view]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 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 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 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 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 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 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 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 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 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 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 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 ML20086H0561975-10-31031 October 1975 Telecopy AO 75-71:on 751030,isolation Valve SV 3978B Failed. Cause Under Investigation.Corrective Action to Be Determined 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 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 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 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 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 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 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 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 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 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 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 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 ML20086F9811975-10-10010 October 1975 AO 75-64:on 751002,upper Isolation Valve to LS-2-3-231C Found Closed.Caused by Technician Error.Technicians Involved Interviewed & Seriousness of Error Stressed ML20086H1171975-10-0909 October 1975 AO 75-64:on 750929,main Steam Line High Flow Switch DPIS-3-2-116A Found to Trip at Value Slightly Higher than Tech Spec.Caused by Setpoint Shift.Device Checked for Setpoint Repeatability & Recalibr ML20086H1011975-10-0707 October 1975 Telecopy AO 75-66:on 751006,RCIC Inboard Steam Supply Isolation Valve MO-3-13-15 Failed to Close.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086F9741975-10-0303 October 1975 Telecopy AO 75-65:on 751015,alarm Received Indicating Sampling Sys Exhaust Pump Suction Low.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086H1111975-10-0303 October 1975 Telecopy AO 75-65:on 751002,drywell Radiation Monitor Inoperable.Cause Under Investigation.Corrective Action to Be Determined After Investigation ML20086F9861975-10-0303 October 1975 Telecopy AO 75-64:on 751002,upper Isolation Valve to LS-2-3-231C Found Closed.Caused by Technician Error. Technicians Involved Interviewed & Seriousness of Error Stressed ML20086F9891975-09-30030 September 1975 Telecopy AO 75-63:on 750929,outer Isolation Valves 86C & 86D Closed in 1.7 & 2.3 S,Respectively.Caused by Insufficient Hydraulic Fluid in Valve Actuator.Hydraulic Fluid Added & Adjustments Made to Closing Speed ML20086G4221975-09-30030 September 1975 AOs 50-277-75-62 & 50-278-75-61:on 750920,main Stack Flow Transmitters Failed.Caused by Lightning Strike.Damaged Components Replaced.Util Begun Study to Provide Permanent Resolution of Problem ML20086H1201975-09-29029 September 1975 Telecopy AO 75-64:on 750929,main Steam Line High Flow Switch DPIS-3-2-116A Found at Value Slightly Higher than Specified by Tech Spec.Caused by Setpoint Shift.Device Checked for Setpoint Repeatability & Recalibr ML20086H1301975-09-22022 September 1975 Telecopy AO 75-62:in 750921,RHR Head Spray Stay Fill Vent LS-5223 Found Inoperable.Caused by Binding in Switch Float Assembly.Stay Fill Tank Refilled & Switch Will Be Repaired ML20086G4261975-09-22022 September 1975 Telecopy AOs 50-277-75-62 & 50-278-75-61:on 750920,main Stack Flow Transmitters Failed.Caused by Lightning Strike. Damaged Components Replaced 1976-01-08 Category:TEXT-SAFETY REPORT MONTHYEARML20217K9931999-10-14014 October 1999
[Table view]Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 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 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.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 ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. 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 ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30 |
Text
_ - _ _ _ _ _ _
PHILADELPIIIA ELECTRIC COMPA!."' 'f ,
- adh 14tece Atonic Fouer Stn a j Dolta, Pennsylvania 17314 March 24, 1975 J
Hr. Janco P. O'Reilly, Director Offica of Inspection and Enforcement ,# (.4 4 , #
bg
- N n States !!ucicar Regulatory Co-Msofon 631 Park Avenua 19405 q( ' h j;
King of Prunnia, Pennsylvania
- Subfect: Abnorn s1 Occurrenen 24-Hour tiotifiestion
- Confinning J. F. Franz' phone canveenstion with Dr. CharJew Calina, $
Ret; ion 1 United Staten 1:ucluex Regulatory corariasion on twch 21, 1975.
Refercucc: Licotuto !Tumber DPR-44 C unt i 11- Sprt ." . m iou Resuscace.
Idulu .h-2.6 Report !!o.s !A. - 17'-75-22 Report Date: March 24, 1975 Occurrenen Dato: Ifarch 21, 1975 Peach Dotton Atomic Power Section .. .
Facility:
R.D. 1, Delta, Pennsylvania 17314 Idantification of Occurrenco:
Failure of SMI Channel C.
Conditions Prior to Occurrence:
Unit 2 at full pownr. .
Deceription of Occurrence:
The "C" SD1 was discovered to be failing downscale during a nor=s1 ocan of control roon instru=ents.
~
Designation of Apparent Cauan of Occurrence:
Blown fuco in povar cupply to drcver.
Annlynto of Occurrence:
Because tha rod block function frca the $31's is bypnosed in the RIM mode, there are no safety icylications ssuociated with this fciluro.
Correctiva Action:
Pre 11ninary innstication rc*ealed no obvious reason for the fuse to blev. The fus vna replaced to return the channel to carvice. Investigation concicua:s.
Failure Data:
!!one provices. 8401230050 750331 PDR ADOCK 05000277 S PDR Very truly yours.
[MjbS[
U. T. Ullrich, Cupctintcclant Peach Ecttosa Atomic Pow.er Station 1
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