ML20080J265
| ML20080J265 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 09/21/1983 |
| From: | Toole R GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 5211-83-270, RO-83-028, RO-83-28, NUDOCS 8309260274 | |
| Download: ML20080J265 (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 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 ML20080T0361983-09-19019 September 1983 RO 83-26:on 830917-18,all Main Steam Safety Valves Tested. 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Caused by Deficient Administrative & Design Controls 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 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 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 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 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 ML20126B4771980-02-11011 February 1980 RO 80-03/1P:makeup Pump Discharge Check Valves MU-V-734A/C Found W/Damages Locking Devices on Valve Seat Holddown Bolts.Cause Unstated.Matls Analysis on Failed safety-related Crane Tilting Disc Check Valves Being Conducted ML20062E6271978-12-0505 December 1978 RO 78-31/4P:river Water Temp Change Exceeded Tech Spec Limits.Caused by Low Inlet Temp & High Ambient Temp & Relative Humidity,Resulting in Inability of Mechanical Draft Cooling Towers to Cool Discharge Water Properly ML20085A5011975-06-27027 June 1975 Ro:On 750613,power Relief Valve Actuated at 2,257 Psig & Failed to Close,Resulting in Rupture of Quench Tank Rupture Disc & Violation of Fuel Compression Curve & Cooldown Rates. Caused by Incorrectly Positioned Pilot Valve Lever ML20244A8031975-04-0909 April 1975 Nonroutine 30-Day Rept 75-04:deficiency Found in Scope of Analysis Utilized in Deriving Power Vs Rod Withdrawal Limits Per Tech Spec Figures-3.5-2a,2b & 2c.Mgt Review Underway 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
Nuclear carricr""
Route 441 South Midahtown, Pennsylvania 17057-0191 717 944 7621 TELEX 84-2386 Writer's Direct Dial Number:
September 21, 1983 5211-83-270 Dr. T. E. Murley Region I, Pegional Administrator U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Licensee Event Report 83-028 This is to confirm the conversation between Mr. R. Conte and Mr. F. Young, Region I, NRC, and Mr. M. Nelson, Supervisor Unit 1 Review Program, at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on September 20, 1983. The event described below was declared' report-able at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on September 20, 1983.
On September 20, 1983, a manual inside containment isolation valve (IA-V20) in the Instrument Air penr.tration to the Reactor Building was found to be open contrary to the requirements of Technical Specification 3.6.1 and 1.7.c and Operating Procedure 1101-3, " Containment Integrity and Access Limits".
This valve appeared to be closed. The stem b2shing in the valve yoke had backed out of the yoke toward the valve handwheel such that when turned in the closed position the handwheel was mechanically limited from turning.
The outside containment isolation valve (IA-V6) on this penetration was to replace the locked closed.
Immediate corrective action has been t-o IA-V20 valve bonnet with one which has a properly ca ed yoke stem bushing and to close and leak test this valve. This item is considered reportable in accordance with Technical Specification 6.9.2.A.2.
The details of this occurrence and the corrective actions to prevent recur-rence will be provided within 14 days.
Sincerely, M&.
8309260274 830921 R
. Toole PDR ADOCK 05000289 Operations & Maintenance S
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R. Conte J-GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation O