ML19330C304
| ML19330C304 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 08/04/1980 |
| From: | Herbein J METROPOLITAN EDISON CO. |
| To: | |
| References | |
| TLL-364, NUDOCS 8008080209 | |
| Download: ML19330C304 (1) | |
Similar Documents at Three Mile Island | |
|---|---|
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 |
Text
Metropolitan Edison Cornpany
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Post Of fice Box 480 J
Middletown, Pennsylvania 17057 717 9444041 Writer's Direct Dial Number August 4, 1980 TLL 364 Office of Inspection and Enforcement Atta:
B. H. Grier, Director Region I Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit I (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Radiation Emergency Exercise During the Radiation Emergency Exercise conducted at Three lEle Island Nuclear Station on July 16, 1980, a problem was encountered concerning the use of the Emergency Notification System (ENS) phone line. Although the ENS functicned properly for the initial notification of an emergency condition, use of the ENS became uncertain when an attempt to patch in Region I was made.
Observer s reported fading on the line and considerable background noise making accurate information transfers questionable.
In an attempt to circumvent the problem, a commercial Bell System line was tried with the same resulting problems. In considering the importance of the ENS, it is felt that these problems should be brought to your attention for timely resolution.
Additionally, per March 14, 1980 letter to D. Haverkamp, we have recommended that (1) a microphone headset be made available for connection to the ENS phone in the Control Room and Shif t Supervisor's office to allow mobility of the ENS phonetalker and (2) the ENS and HPN telephones in the Near-Site Emergency Operations Facility be equipped with wall jacks.
These phones may then be stored in the Radiation Emergency Storage Locker thereby preventing inadvertent use.
Sincerely, Signed J. G. Herbein J. G. Herbein Vice President TMI-I 00/
JCH:GJG:lma cc:
J. T. Collins
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D. Haverkamp 6
C. Gallina
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