ML19308A511
| ML19308A511 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 01/12/1978 |
| From: | Ohanlon J METROPOLITAN EDISON CO. |
| To: | |
| References | |
| NUDOCS 7910250743 | |
| Download: ML19308A511 (1) | |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20202F2341986-07-0303 July 1986
[Table view]Ro:On 860621,canister Seal Installation Tool Removed from Reactor Vessel Following Seal Installation on Defueling Canister D200.Radiological Survey Not Performed Prior to Storage.Caused by Task Supervisor Failure to Require Survey ML20133C4691985-09-16016 September 1985 Ro:On 850821,make-up Auto Power Failure Resulted in Partial Loss of Instrumentation & Control sys/non-nuclear Instrumentation Power.Caused by Shortage Due to Worn Insulation on Coiled Connector Cable.Cable Replaced ML20083F1451983-12-14014 December 1983 RO 83-046:on 831213,review of Cable Separation for Makeup Pump Low Lube Oil Pressure Trip Circuit Revealed That Cables for Makeup Pumps a & C Improperly Separated & Circuits Improperly Classified ML20082H1041983-11-15015 November 1983 RO 83-044:on 831114,AE Site Walkdown Revealed Redundant Circuits in Emergency Feedwater Auto Initiation Circuitry Found Installed/Routed in Same Cable Bundle.Cables Will Be Separated in Jan 1984 ML20082A8721983-11-0808 November 1983 RO 83-043:on 831106,motor Driven Emergency Feedwater Pump EF-P-2A Found Inoperable for Greater than 48 H W/Rcs at Greater than 250 F.Cause Under Investigation ML20081M7731983-10-25025 October 1983 RO 83-040:on 831014,radiation Monitor RM-L-12 Not Installed on Industrial Waste Filter Sys Common Discharge Per Tech Specs,Due to Failure to Receive Amend 88 to License DPR-50, Changing Tech Specs.Public Safety Maintained ML20082K9621983-10-19019 October 1983 RO 83-039:on 831018,after Hays Gas Analyzer Removed from Svc to Perform Calibr,Waste Gas Sys Vent Header Not Sampled for 6.5 H.Cause & Corrective Action Will Be Described in Followup Rept ML20078N4031983-10-0303 October 1983 RO 83-032:both Thermal & Seismic Stress on Instrument Tubes Reevaluated as Followup to Internal Matl Nonconformance Rept.Operability Stresses Below ASME III Criteria Revealed ML20080P6041983-10-0303 October 1983 RO 83-032:on 830930,thermal & Seismic Stress Criteria on Instrument Tubes Not Met.Fatigue Characteristics Revealed Allowable Number of Cycles Exceeds Actual Number of Heatup & Cooldown Cycles Experienced ML20080J2651983-09-21021 September 1983 RO 83-028:on 830920,manual Inside Containment Isolation Valve (IA-V20) in Instrument Air Penetration to Reactor Bldg Found Open.Caused by Stem Bushing in Valve Yoke Backed Out of yoke.IA-V20 Valve Bonnet Replaced ML20080T0361983-09-19019 September 1983 RO 83-26:on 830917-18,all Main Steam Safety Valves Tested. All But One Valve Lifted Above Allowed Lift Point Tolerance of +1% of Setpoint.Caused by Using Incorrect Main Steam Header ML20080T0331983-09-19019 September 1983 RO 83-25:on 830916,containment Isolation Valve Found Open While Containment Integrity Required.No Threat to Health & Safety Since Second Boundary Remained Closed.Cause & Corrective Actions Expected in 14-day Followup Rept ML20078A6011983-09-19019 September 1983 Ro:On 830916,containment Isolation Valve Found Open While Containment Integrity Required.Cause of Incident & Corrective Actions to Prevent Recurrence to Be Described in 14-day Followup Rept ML20085H6031983-08-29029 August 1983 Ro:On 830827,high Deuterium Alarm in Waste Gas Hold Up Sys Received.Caused by Leakage from Makeup Tank Gas Space Into Vent Header Due to Incorrect Valve Lineup ML20024E6601983-08-0404 August 1983 RO 83-18:on 830804,during Maint Insps on Hydraulic Snubbers, Two Small Bore Snubbers Identified as Being Installed on RCS Hot Leg Vent Piping Downstream of Valves RC-V15A & B.Caused by Personnel Error ML20073R0881983-04-18018 April 1983 RO 83-11:on 830326,DHR 1A Shaft Bearings Failed,Making Pump Inoperable.Caused by Design Change to Pump Bearing Lube Oil Sys.Sys Returned to Original Configuration.Review of Existing Sys in Progress ML20069L3761983-04-18018 April 1983 RO 83-11:on 830326,decay Heat Pump 1A Shaft Bearings Failed,Rendering Pump Inoperable.Caused by Incorrect Design Change to Pump Bearing Lube Oil Sys.Lubrication Sys for Pumps 1A & 1B Returned to Original Configuration ML20069L5481983-03-31031 March 1983 RO 83-008:on 830329,oxygen Concentration in Miscellaneous Waste Storage Tank Gas Space Exceeded Tech Specs.Nitrogen Used to Purge Oxygen from Sys & Oxygen Concentration Reduced within Limits ML20072Q5861983-03-22022 March 1983 Telecopy RO 83-005:on 830321,high Oxygen Content Found in Waste Gas Sys.Caused by Recent Maint Activities.Addl Hydrogen/Oxygen Monitor Scheduled for Installation Prior to Restart ML20070W0821983-02-11011 February 1983 Telecopy of RO 83-003:on 830210,initial Disassembly & Insp of PORV RC-RV2 Revealed Pilot Valve Piston & Spring Corroded in Full Open Position.Failure Analysis Initiated to Determine Cause & Corrective Actions ML20065B5651983-02-11011 February 1983 Telecopy RO 83-003:on 830210,during Insp of PORV RC-RV2, Corrosion Identified in Inconel & Austenitic Steel Parts. Pilot Valve Piston & Spring Also Found Corroded.Cause Under Analysis ML20064N9211982-09-0303 September 1982 RO 82-012:on 820902,Tech Spec Re Limiting Condition for Operation Was Not Met for Station Effluent Line Monitor Setpoints RML-7.Caused by Setpoints Not Being Set Per Offsite Dose Calculation manual.RML-7 Setpoints Reset ML20054G5881982-06-0404 June 1982 RO 82-20:on 820603,determined That Recent Overflow of Auxiliary Bldg Sump Occurred Due to Influx of Rainwater from Borated Water Storage Tank Recirculation Pump Encl Sump. Caused by Deficient Administrative & Design Controls ML20053C9041982-05-19019 May 1982 RO 82-15:on 820517,incore Thermocouple 14-D Was Inoperable. Details Will Be Included in Followup Rept ML20052H6921982-05-18018 May 1982 Ro:On 820428,five Smoke Detectors Inside Containment Found Inoperable Since Brief Responses Not Detected on Control Room Panels.Apparently Caused by Circuitry Problem.Fire Indicating Unit Replaced.Retesting Scheduled for 820526 ML20053C9711982-05-11011 May 1982 RO 82-007:on 820509,oxygen Concentration Exceeded Tech Specs Limit of 2% After Reactor Coolant Bleed Tank Was Returned to Svc After Maint.Nitrogen Purge Initiated on Tank to Reduce Oxygen.Erroneously Numbered ML20079F8491982-05-11011 May 1982 RO 82-008:on 820408 & 0509,oxygen Concentration Exceeded Tech Spec Limit After C Reactor Coolant Bleed Tank Returned to Svc Following Maint.Tech Spec Will Be Revised to Take Maint Effects Into Account ML20050D5331982-04-0202 April 1982 RO 82-011/01L-0:on 820303,re Potential Bypass Path of Several Ventilation Sys Filtration Units.Followup Rept Will Be Submitted by 820406 ML20050A5431982-03-18018 March 1982 Ro:On 820318,water W/Ph of 3.5 Was Discharged from Secondary Waste Water Neutralizing Tank WT-T-1 Into Plant Discharge Effluent Stream.Caused by Accidental Overflow of Approx 2,500 Gallons of Water from Neutralizing Tank ML20039C6331981-12-23023 December 1981 RO 81-14:nine Pipe Support & Structural Interfacing Areas Identified Requiring Further Evaluation & Potential Corrective Action.Failure of Pipe Supports Could Damage safety-related Components.Followup Rept Expected in 14 Days ML20031D9451981-07-31031 July 1981 Ro:On 810629,steam Void Formed in RCS Loop a Hot Leg During Pressurizer Cooldown.Caused by de-energizing Pressurizer Heaters to Reduce RCS Pressure & Slow Leakage from Loop B Instrument Root Valve.Heaters Repressurized ML19350F0841981-06-16016 June 1981 RO 81-015/1P:on 810613,control Room Ventilation Sys Monitor HP-R-220 Alarmed,Indicating Temp Inversion.Caused by Failure of Interlock Key Switch to Return to Recirculation Mode, Which Prevented Automatic Actions ML20126L5161981-05-11011 May 1981 RO 81-13/1P:on 810508,incore Thermocouple L-11 Failed. Thirty-two Thermocouples Remain Operable ML20126J8521981-04-21021 April 1981 RO 81-10/1P:on 810420,discovered Failure to Meet Requirements of Shift & Daily Checks Surveillance Procedures for post-accident Instrumentation & Radiation Monitoring Instrumentation.Addl Info Will Be Provided ML19345F2531981-02-0202 February 1981 Corrected RO 81-02/1P:on 810119,emergency Diesel Generator Failed to Operate.Prompt Notification Ltr of 810128 Had Identified 801226 as Generator Failure Date ML19340E4801980-12-24024 December 1980 RO 80-56/1P:on 801219,radiation Monitor HPR-220 Placed in Defeat,Causing Condition Where Radiation Signal Would Not Place Control Room Ventilation Into Recirculate.Caused by Instrument Malfunction.Monitor Repaired ML20049A3761980-12-15015 December 1980 RO 80-56/1P:on 801212,determined That Core Flood Tank a Had Failed.Cause Not Stated.Details Will Be Included in Followup Rept ML20062K0701980-11-17017 November 1980 RO 80-53/1P:on 801108,incore Thermocouples N-3 & N-9 Determined to Be Failed ML20062K0691980-11-17017 November 1980 RO 80-52/1P:on 801113 Following Leak Test of Personnel Airlock 2,inner Door Leak Rate Test Failed to Meet Required Tech Spec Limit.Door Could Not Be Returned to Svc within 24-h Required Limit ML19345C3401980-11-10010 November 1980 RO 80-50/1P:on 801108,incore Thermocouple 9-H Failed.Further Details to Follow ML20062K0531980-10-28028 October 1980 RO 80-48/1P:on 801027,four Relief Valves W/Unauthorized ASME UV Code Symbol Stamp Discovered.Followup Action Being Initiated ML20062J4281980-10-20020 October 1980 RO 80-410:determined That Replacement Coils Being Installed in Response to IE Bulletin 79-01A Have a Range Lower than Station Battery Voltage Range.Coils Could Potentially Fail If Maintained at Voltages Above Normal Operating Range ML20030A3121980-09-26026 September 1980 RO 80-044/1P:on 800924,during Planned Reactor Bldg Entry, Leak Rate Test of Outer Door on Personnel Airlock 1 Revealed That Door Did Not Meet Required Limits.Door Could Not Be Returned to Svc within 24-h.Details Will Follow ML19337A8631980-09-23023 September 1980 RO 80-17:determined Insufficient Documentation to Demonstrate That Brakes on Motor Operators for Purge Valves AH-V1B & AH-V1C Environmentally Qualified.Redundant Valves Fully Qualified ML19331C3761980-08-11011 August 1980 RO 80-37/IP:on 800807,when Reactor Personnel Airlock Was Reclosed After Being Open for Work,Leak Rate Failed to Meet Tech Specs.Door Could Not Be Returned to Svc for 24-h.Cause Not Stated.Door Repaired ML19338C6611980-08-11011 August 1980 RO 80-36/1P:confirms 800808 Telcon Re Delay in Performance of Boron & Hydrogen Analysis of 800804 RCS Sample by B&W Labs.Caused by Contamination in B&W Lab.Lab Problem Rectified & Analysis of Samples Will Resume ML19330C3041980-08-0404 August 1980 Ro:On 800716,during Radiation Emergency Exercise,Use of Emergency Notification Sys Phone Line Became Uncertain, Making Accurate Info Transfers Questionable.Recommends That Microphone Headset Be Made Available to Allow Mobility ML19330B6461980-07-31031 July 1980 RO 80-33/1P:on 800730,info Received from Gould/Ite Re Failure W/Pneumatic Timer Unit J20T3 That Had Been Returned for Evaluation (Ref Special Rept 80-003/99X-0,800228). Details Will Be Included in follow-up Rept ML19326E2061980-07-22022 July 1980 RO 80-15/4P:confirming 800722 Telcon,On 800721,river Water Discharge Temp Was More than 3 F Below Inlet River Water Temp for Approx 6-h.Incident Will Be Reviewed to Determine Corrective Action.Review to Be Included in Followup Rept ML19321A4691980-07-17017 July 1980 RO 80-30/1P:on 800717,surveillance Testing of Inner Personnel Airlock Containment Door Indicated That Leakage Past Inner Door Seals Exceeded Tech Spec Limit.Subsequent Surveillance Testing of Outer Door Was Satisfactory 1986-07-03 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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D Mr. Bruce H. Grier Directorate of Regulatory Op2. atien WW Region el o r D E
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Nuclear Regulatory Co nission
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3 630 Park Avenue 6L King of Prussia, PA 19406 Operating License DPR-50 Docket 50-289
Subject:
Reportable Occurrence No. 78-2/IP
Dear Mr. Grier:
This telegran is to docu ent the conversation between Mr. P. J. r.ellegg,
("RC Inspector) and Mr. J. P. O'Hanlon (TMI-I Superintendent) at 1045 heurs on January 12, 1978.
l A violation of the Technical Specification 3.18.3.7.a was recognized at 0730 on January 12, 1978, in that a continuous fire watch was not established for a period of atout 63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br /> af ter the "A" Ecergency Diesel Poon Sprinkler Isolation Valve was closed. This incident is considered Reportable under T.S. 6.9.2A.7.
FS-V-156 was closed et about 0500 on January 10, 1978, but due to ac incorrect interpretation of the recently issued Fire Service Technical Speciti-cation, only a periodic diesel rooi fire inspection was n de until abcut 1030 on January 12, 197R. at v.hich tire a continuous fire watch was established.
Further details of this incident and the corrective acticos taken will be forwarded to you in the 14 day report.
Very truly yo;rs, A
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