ML19262A177
| ML19262A177 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/13/1974 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 7910260503 | |
| Download: ML19262A177 (1) | |
Similar Documents at Three Mile Island | |
|---|---|
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 |
Text
/
METRO?OUTAN EDISC* COMPANY sussimmorcrusut ,ucununtsccoonno TELEPHONE 717- /
ST OFFICE BOX 480 MIDDLETOWN. PENNSYLVANIA 17057 Septeeber 13, 1974
- f6 Mr. J.P. O'Reilly, Director ]D*'PlD Directorate Of Regulatory J s L A\ d [R 7 0 "\dM _,
Region I 631 Park Avenue
. King Of Prussia Pa. 19406
, Operating nse DPR-50 Docket 50f269
Subject:
Abnomal Occurrence Ho. A0 74-15
Dear Mr. C'Reilly:
This telegram is to confim the telecon betxeen Mr. Burt Davis (Region I-AEC),
and J.G. Herbein (TMI-Station Superintendent) at 2000 hrs.12 Septecer 1974.
The following report is sub:ritted in accordance with paree aph 6.7.2.a (page
(-11) of the technical specifications.
On 11 Septer:ter while perfcrming Quarterly Surveillance Procedure 1303-5.1,
" Reactor Building Cooling and Isolation Syste::: Logic Channel and Co,.ponent Te3t," Reactor Building Spray Valve, BS-V1B failed to open as the result of a bics:n control fuse.
The failure occurred while testing the Engineered Safeguards two out of three, 4 psig, logic channels.
The duplicate (redundant) cocponent (BS-V1A) was tested and proved to be operable.
The investigation subsequently revealed a wiring error in the Engineered Safeguards Actuation logic output to BS-V1B. The wirir,g error connected the logic contacts of 65-VlB with a DC circuit. The wiring error was sub-sequently corrected a.,d BS4V1B was successfully tested.
Very truly yours,
/
J.G. Herbein 'l ,
Station Superintendent THI Nuclear Station hen
- <(
JGi/ct::n
.'if 910 fdO M3 3 1482 153