ML20073R088
| ML20073R088 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 04/18/1983 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 5211-83-120, RO-83-11, NUDOCS 8305030436 | |
| Download: ML20073R088 (2) | |
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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. 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 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 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 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 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 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 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 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 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
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o GPU Nuclear Corporation G
U tuclear
= = neeSs48o Middletown, Pennsylvania 17057 717 944-7621 TELEX 84 2386 Writer"s Direct Dial Number:
April 18, 1983 5211-83-120 Regional Administrator Region I 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 LER 83-11 This letter confirms the conversations on March 28, 1983 (R. J. Toole to R.
Conte), April 11,1983 (M. A. Nelson to A. Fasano and F. Young) and on April 15, 1983 (M. A. Nelson to A. Fasano, final declaration of reportability) concerning reportability of following event.
At 3 p.m. on April 15, 1983, it was determined that an incident involving the Decay Heat Removal Pumps was reportable per Tech Spec 6.9.2.A.9.
The incident occurred on March 26, 1983 and has been under investigation since.
On March 26, 1983, the Decay Heat Pump 1A shaft bearings failed, making the pump immediately inoperable. The investigation determined that a new design change that was made to the pump bearing lube oil system did not work correctly.
Because of an inadequate understanding of the new oiling design, the operators removed the manual oiler from the pump and because of inadequate calibration of the new oiler, the bearing lost lubrication.
Action was required to return the lubrication system for both DH-PlA & 1B to their original configuration. This failure is, therefore, reportable under Tech. Spec. 6.9.2. A.9, " Performance of structures, systems, or com-ponents that require remedial action...".
In addition to returning the system to their original configuration, a review of the existing oiler design is underway.
8305030436 830418 PDR ADOCK 05000289 s
PM GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation g
p w
Regional Administrator 5211-83-120 The details of this occurrence and correcti- 'ction to prevent recurrence will be provided in a follow-up report.
Sincerely,
$1 b
Director, TMI-1 IIDil:CWS:vj f cc:
J. Van Vliet R. Conte
.