ML19210A180
| ML19210A180 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 06/06/1975 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19210A178 | List: |
| References | |
| NUDOCS 7910240903 | |
| Download: ML19210A180 (1) | |
Similar Documents at Three Mile Island | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML19210A1511976-02-12012 February 1976
[Table view]Abnormal Occurrence 76-7/1P:on 760212,empty Snubber Fluid Reservoir Found at Location DHH-198.Leakage Due to Damaged Seal.Snubber Removed & Replaced ML19322A4301976-02-0505 February 1976 Abnormal Occurrence 76-6/1P on 760204:radiation Leak Detection Sys Out of Svc for 22-h.No Reactor Bldg Atmospheric Samples Taken.Caused by Cover Plate to Monitor Left Open Following Insp.Procedures Reviewed W/Personnel ML19210A1581975-12-26026 December 1975 Abnormal Occurrence 50-289/75-43:on 751218,one of Six Pressure Switches Tripped at Less Conservative Limits than Tech Specs During Channels Surveillance Test.Caused by Calibr Drift in Associated Pressure Switch PS-290 ML19210A1451975-12-19019 December 1975 Abnormal Occurrence 50-289/75-42:on 751210,outside Containment Isolation Valve for Steam Generator Sample Line CA-V5B Failed to Close.Caused by Valve Manual Operator Inadvertently Left Open by Reactor Personnel ML19210A1731975-11-25025 November 1975 Abnormal Occurrence 50-289/75-40:on 751112,stuck Contacts on Diesel Generator 1A Voltage Relays Threatened Function of Engineered Safety Feature.Caused by Pitting of Relay Contact.Relays Checked at Each Startup Pending Design Mods ML19261F1481975-11-24024 November 1975 Abnormal Occurrence 50-289/75-41:on 751114,personnel Failed to Strictly Follow Drain & Blanketing Procedure.Vented Center Control Rod Drive Mechanism Allowed Radioactive Gas Into Reactor Bldg.Personnel Counseled on Proper Procedures ML19210A1831975-11-21021 November 1975 Abnormal Occurrence 50-289/75-39:on 751112,control Rod 4 in Group 7 Dropped Into Core,Resulting in Asymmetrical Rod Signal & Automatic Power Reduction.Caused by Failure of Stator Winding.Stator Winding Replaced & Tested ML19210A1891975-10-31031 October 1975 Abnormal Occurrence 50-289/75-38:on 751021,control Rod Verification Program Not in Compliance W/Tech Specs.Caused by Procedure Misinterpretation.Revised Surveillance Program Will Clearly State Requirement of Individual Rod Movement ML19210A1911975-10-31031 October 1975 Abnormal Occurrence 50-289/75-37:on 751021,blocked Strainer on Outlet to Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Improper Design Allowing for One Strainer W/No Bypass Caused Blockage ML19210A2021975-10-29029 October 1975 Abnormal Occurrence 50-289/75-36:on 751019,auxiliary Operator Failed to Obtain Radiation Work Permit & Carry Monitoring Device.Caused by Improper Administrative Procedures ML19210A1971975-10-21021 October 1975 Abnormal Occurrence 75-37:on 751021,blocked Strainer on Outlet of Boric Acid Mixtank Decreased Flow Rate.Plant Shutdown Followed to Replace Strainer.Plant Returned to Svc in 15 Minutes ML19210A2151975-10-20020 October 1975 Abnormal Occurrence 50-289/75-35:on 751010,improper Mix of Boric Acid Crystals Caused Blockage in Mix Tank.Crystals Settling to Bottom of Tank Clogged Line to Reclaimed Boric Acid Storage Tank.Mixture Mod Should Correct Failures ML19210A2211975-10-10010 October 1975 Abnormal Occurrence 75-37:on 751010,during Transfer of Boric Acid from Storage Tank to Reclaim Tank,Blockage Noticed in Outlet Line.Caused by Boric Acid Crystals Settling to Drain Due to Improper Mixture ML19210A2241975-10-0808 October 1975 Abnormal Occurrence 50-289/75-34:on 750928,inoperative Hydraulic Shock Suppressor Threatened Function of Engineered Safety Feature.Low Fluid Level in Snubber Caused Failure. All Other Snubbers Checked Satisfactorily ML19322A4371975-09-30030 September 1975 Abnormal Occurrence 75-34 Re Disconnected Hydraulic Snubber within Reactor Bldg Secondary Shield.Investigation of Circumstances Incomplete.Snubber Replaced During Ongoing Seal Replacement Program ML19210A2461975-09-26026 September 1975 Abnormal Occurrence 50-289/75-31:on 750917,core Flood Tank Water Level Below Tech Specs Requirements.Caused by Incorrect Reading on Lower Reading Channel CF2-LT3.Channel Will Now Be Monitored & Personnel Informed on Procedures ML19210A2411975-09-26026 September 1975 Abnormal Occurrence 50-289/75-33:on 750917,de-ice Makeup Valve NR-V-4A Failed in Open Position.Failure Caused by High Resistance Contact in Closing Control Circuit Not Fully Energizing.All Control Contacts to Be Checked & Cleaned ML19210A2391975-09-26026 September 1975 Abnormal Occurrence 50-289/75-32:on 750918,incorrect Open Position of Air Supply Valves PP-V-47 & 179 Could Have Prevented Proper Functioning of Door Seals in Event of Emergency Safeguards Actuation.Jj Colitz 750919 Ltr Encl ML19210A2451975-09-19019 September 1975 Abnormal Occurrence 75-33 Re Failure of de-ice Makeup Valve NR-V-4A to Close Using Control Room Remote Pushbutton.Caused by High Resistance Contact in Closing Control Circuit. Contact Cleaned,Tested & Returned to Svc ML19322A4361975-09-18018 September 1975 Abnormal Occurrence 75-31 Re Low Borated Water Level in Core Flood Tank B.Caused by Improper Level Channel Transmitter LT3 Readout.Transmitter Adjusted ML19210A1791975-09-0505 September 1975 Abnormal Occurrence 50-289/75-29:on 750827,reactor Bldg Purge Supply Valve AH-V-1D Failed to Close Prior to Engineered Safeguards Test.Caused by Corroded Robotarm Actuator.Robotarm Actuator Lubricated ML19210A2251975-09-0505 September 1975 Abnormal Occurrence 50-289/75-30:on 750827,valve CF-V-2B of Core Flood Tank B Sample Line Isolation Failed to Close Upon Receipt of Engineered Safeguards Actuation Signal.Caused by Valve Binding Against Valve Stem ML19210A1811975-09-0202 September 1975 Abnormal Occurrence 50-289/75-28:on 750823,MS-V-13A Valve Turbine Drive Emergency Feed Pump Failed to Remain Open. Caused by Control Circuit Pressure Switch Failure,Due Possibly to High Ambient Temp ML19210A1871975-08-29029 August 1975 Abnormal Occurrence 50-289/25-27:on 750821,crack & Leak Found in Auxiliary Makeup Pump a Suction Vent.Caused by Fatigue Due to Vibration.Cracks Repaired & Hydrostatically Tested.Failed Pipe Section Replaced ML19322A4351975-08-28028 August 1975 Abnormal Occurrence 75-30:on 750827,core Flood Tank B Sample Line Isolation Valve CF-V2B Failed to Close Following Engineered Safeguards Signal.Valve Manually Closed Using Handwheel ML19210A1861975-08-27027 August 1975 Abnormal Occurrence 75-29:on 750827,reactor Bldg Supply Valve AH-V-1D Failed to Fully Close.Investigation Into Cause Underway ML19210A1841975-08-23023 August 1975 Abnormal Occurrence 75-28:on 750820,during Test of Turbine Drive Emergency Feed Pump,Associated Valve Failed to Remain Open.Caused by Failed Pressure Switch ML19210A1901975-08-21021 August 1975 Abnormal Occurrence 75-27 on 750821:leaks Found in Socket Weld Joint at Makeup Pump a & Suction Line Connection W/Pump Suction Header.Cause of Problem Under Investigation ML19210A1941975-08-0101 August 1975 Abnormal Occurrence 50-289/75-26:on 750724,high Reactor Coolant Pressure Trip Set Points Less Conservative than Tech Specs.Caused by Calibr Drift.Specs Will Be Changed to Account for Instrument Error ML19210A1951975-07-31031 July 1975 Abnormal Occurrence 50-289/75-25:on 750721,failure of Diesel Generator a Frequency Relay to Actuate,Threatening Nonperformance of Diesel Generator.Cause Presently Unknown ML19210A2001975-07-25025 July 1975 Abnormal Occurrence 50-289/75-23:on 750716,auxiliary Relay to Generator 1B Failed to Energize on Demand.Caused by Mfg Defect.Failed Relay Replaced & Remaining Relays Inspected ML19210A2071975-07-25025 July 1975 Abnormal Occurrence 50-289/75-24:on 750716,during Removal of River Water Pump NR-P1B from Svc,Discharge Valve Failed to Close.Caused by Open Phase on Winding Due to Severe Heat Resulting in Single Phasing of Other Windings ML19210A1991975-07-22022 July 1975 Abnormal Occurrence 75-25:on 750722,three Frequency Relays to Steam Generator a Found in Dropped Out State.Relays Replaced & Returned to Svc.Cause of Failure Yet to Be Determined ML19210A2171975-07-21021 July 1975 Abnormal Occurrence 50-289/75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump Suction Vent Line MU-PIA Leading to Valve MU-V156A.Caused by Improper Spacing Between Moving Anchor & First Pipe Restraint ML19210A2051975-07-18018 July 1975 Abnormal Occurrence 75-23:on 750716,one of Three Auxiliary Relays of Diesel Generator 1B Breaker G11-02 Failed. Remaining Relays Tested Satisfactorily.Cause of Failure Under Investigation ML19210A2121975-07-18018 July 1975 Abnormal Occurrence 75-24:on 750716,river Water Pump Discharge Valve Failed Due to Low Valve Motor Winding Resistance & Winding Motor Overheating ML19210A2221975-07-11011 July 1975 Abnormal Occurrence 75-22:on 750711,leaks Found in Socket Weld Joints of Makeup Pump a Suction Line Vent.Caused by Pump Vibration ML19210A2311975-07-0303 July 1975 Abnormal Occurrence 50-289/75-21:on 750625,coolant Temp Trip Bistable Channel C Failed to Trip During Test of Reactor Protection Sys.Caused by Defective Printed Circuit Board Solder Joint in Signal Converter ML19210A2371975-06-27027 June 1975 Abnormal Occurrence 50-289/75-19:on 750618,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Caused by Channel C Trip Setpoint Out of Calibr Due to Instrument Drift ML19210A2301975-06-27027 June 1975 Abnormal Occurrence 75-03:on 750626,noble Gas Released to Auxiliary Bldg.Probable Cause:Evaporator Malfunction While Filling Makeup Tank or Coolant Bleed Tank.No Tech Specs Exceeded ML19210A1621975-06-27027 June 1975 Abnormal Occurrence 50-289/75-18:on 750615,QA Documentation from Vendor Found Inadequate for Repaired Decay Heat River Water Pump Motor Shaft.Caused by Lack of Administrative Controls ML19210A2351975-06-25025 June 1975 Abnormal Occurrence 75-21:on 750625,reactor Protection Sys Channel C Failed During Surveillance Test.Caused by Coolant Temp Trip Bistable Failure to Trip Due to Component Failure in Signal Converter ML19210A1721975-06-25025 June 1975 Abnormal Occurrence 50-289/75-17:on 750615,reactor Bldg Purge Isolation Valve Failed Local Leak Rate Test.Caused by Improper Valve Adjustment Procedures & Matl Defects Not Allowing Long Term Retention of Adjustment ML19308A5371975-06-23023 June 1975 Abnormal Occurrence 75-20:on 750622,while Returning to Full Power Operation After Forced Power Reduction,Reactor Power Increased Above Power Level Cutoff Before Xenon Reactivity Approached Stability.Procedures Under Review ML19210A2431975-06-19019 June 1975 Abnormal Occurrence 75-19:on 750618,less Conservative Variable Low Reactor Coolant Sys Pressure Trip Setpoint for One Channel of Reactor Protection Sys Violated Tech Specs. Caused by Instrument Drift for Channel C Setpoint Calibr ML19210A1661975-06-17017 June 1975 Abnormal Occurrence 75-18:on 750615,repaired Motor Shaft to Decay Heat River Water Pump Not Returned W/Proper QA Documentation.Caused by Lack of Administrative Control ML19210A1751975-06-17017 June 1975 Abnormal Occurrence 75-17:on 750615,during Test of Reactor Bldg Purge Isolation Valve Local Leak Rate Test,Two Exhaust Valves Would Not Pressurize to Required Test Pressure.Caused by Valve AH-V1A Failing to Fully Close ML19210A1771975-06-16016 June 1975 Abnormal Occurrence 50-289/75-16:on 750605,variable Low Reactor Coolant Sys Pressure Trip Setpoints Less Conservative than Tech Specs.Specific Cause Not Established. Setpoints Will Be Checked to Assure Proper Calibr ML19291B5291975-06-13013 June 1975 Abnormal Occurrence 50-289/75-15:on 750605,pressure Transmitter Trip Setpoint of Reactor Protection Sys Channel B Tested Out of Calibr.Caused by Trip Setpoint Calibr Drift ML19210A1801975-06-0606 June 1975 Abnormal Occurrence 75-16:improper Trip Setpoints on Variable Low Reactor Coolant Sys Pressure Sys Violated Tech Specs 1976-02-05 Category:TEXT-SAFETY REPORT MONTHYEARML20217G1001999-10-14014 October 1999
[Table view]Errata to Safety Evaluation Supporting Amend 215 to FOL DPR-50.Credit Given for Delay in ECCS Leakage ML20217K4701999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for TMI-1.With ML20216F9231999-09-22022 September 1999 Safety Evaluation Supporting Amend 216 to License DPR-50 05000289/LER-1999-010, :on 990830,discovery of Condition Outside UFSAR Design Basis for Flood Protection Was Noted.Caused Because Original Problem Was Not Corrected by Design Change.Flood Procedure Was Immediately Revised.With1999-09-21021 September 1999
1999-09-30 |
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,;'*'wra--..nETROPOLITAN EDISON COMPANY suassounvorcruent.ruaucununescoaronnouj
' OF'FICE BOX 480 MIDDLETOWN. PENNSYLVANIA 17057 TELEPHONE 717-044 4041 June 6. 1975 Mr. J. P. O'Reilly, Director Directorate of Regulatory Operations Region I C, d %e,0*%'
631 Park Avenue M9 King of Prussia, Pa.19406.cdn, D%.\u Operating License DPR-50 Docket 50-289
Subject:
Abnormal Occumnce No. AD 75-16. ~ .-
Dear Mr. O'Reilly:
This telegram is to confirm the tekecon between Lee Spessard (Region I-DRO), and J. J. Colitz (THI Unit I Superintendent) at 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br />, June 6,1975.
Violation of Technical Specification 2.3.1 in that the variable low reactor coolant system pressure trip setpoints for three RPS channels were found to be less conservative than the setpoint listed in Tabic 2.3.1 (Page 2-9) of the Technical Specifications.
The required and actual trip points for the channels out of specification were as follows:
, Table 2.3-1 Trip Actual Trip Point.Setpoint at 5900 F.
Measured at the
.Channel.(16.25 T out - 77S51 Bistable A.1831.5 1827.4,.B , 1831.5 1828.9 , 1:31.5 1827.5'v/.D-The variable low reactor ecolant system pressure trip setpoints were being checked as part of routine Surveillance Procedure 1303-4.1, "22 actor . Fro-All other reacter protection system trip tection System Surveillance".
setpoints were tested and found to be within Technical Specification limits.
The out-of-specification channels hava been recalibrated and . retested, and the resulting trip setpoints were verified as being within Technical Specification : limits.
, , Very truly yours,'
'3.o/$/MA/ A ffhA$O J. G. Herbein
-, Station Superintendent
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