ML20082H104
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| ML20082H104 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 11/15/1983 |
| From: | Toole R GENERAL PUBLIC UTILITIES CORP. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| 3200-83-544, RO-83-044, RO-83-44, NUDOCS 8312010028 | |
| Download: ML20082H104 (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 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 MONTHYEARML20217K4701999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for TMI-1.With ML20211H5111999-08-31031 August 1999 Non-proprietary Rev 1 to MPR-1820(NP), TMI Nuclear Generating Station OTSG Kinetic Expansion Insp Criteria Analysis ML20211Q3551999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Tmi,Unit 1.With ML20210R4791999-08-13013 August 1999 Update 3 to Post-Defueling Monitored Storage SAR, for TMI-2 ML20210U4791999-07-31031 July 1999 Monthly Operating Rept for July 1999 for TMI-1.With ML20209G0011999-07-0909 July 1999 Staff Evaluation of Individual Plant Exam of External Events Submittal on Plant,Unit 1 ML20210K7651999-07-0909 July 1999 Rev 2 to 86-5002073-02, Summary Rept for Bwog 20% Tp Loca ML20209H8251999-07-0101 July 1999 Provides Commission with Evaluation of & Recommendations for Improvement in Processes Used in Staff Review & Approval of Applications for Transfer of Operating Licenses of TMI-1 & Pilgrim Station ML20209H1421999-06-30030 June 1999 Monthly Operating Rept for June 1999 for TMI-1.With ML20195H0751999-06-0808 June 1999 Drill 9904, 1999 Biennial Exercise for Three Mile Island ML20195H9261999-05-31031 May 1999 Monthly Operating Rept for May 1999 for TMI-1.With ML20209G0351999-05-31031 May 1999 TER on Review of TMI-1 IPEEE Submittal on High Winds,Floods & Other External Events (Hfo) ML20207B6621999-05-27027 May 1999 SER Finding That Licensee Established Acceptable Program to Periodically Verify design-basis Capability of safety-related MOVs at TMI-1 & That Util Adequately Addressed Actions Required in GL 96-05 ML20206R0571999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Tmi,Unit 1.With ML20206D4201999-04-20020 April 1999 Safety Evaluation Granting Exemption from Technical Requirements of 10CFR50,App R,Section III.G.2.c for Fire Areas/Zones AB-FZ-4,CB-FA-1,FH-FZ-1,FH-FZ-6,FH-FZ-6, IPSH-FZ-1,IPSH-FZ-2,AB-FZ-3,AB-FZ-5,AB-FZ-7 & FH-FZ-2 ML20209G0071999-03-31031 March 1999 Submittal-Only Screening Review of Three Mile Island,Unit 1 Individual Plant Exam for External Events (Seismic Portion) ML20205K6851999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Tmi,Unit 1.With ML20210C0161999-03-0101 March 1999 Forwards Corrected Pp 3 of SECY-98-252.Correction Makes Changes to Footnote 3 as Directed by SRM on SECY-98-246 ML20207M8461999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for TMI-1.With ML20196K3561999-01-22022 January 1999 Safety Evaluation Concluding That Although Original Licensee Thermal Model Was Unacceptable for Ampacity Derating Assessments Revised Model Identified in 970624 Submittal Acceptable for Installed Electrical Raceway Ampacity Limits ML20207A9291998-12-31031 December 1998 1998 Annual Rept for TMI-1 & TMI-2 ML20196G4661998-12-31031 December 1998 British Energy Annual Rept & Accounts 1997/98. Prospectus of British Energy Share Offer Encl ML20196F6861998-12-0202 December 1998 Safety Evaluation Accepting Licensee Second 10-yr Interval ISI Program Plan Request for Alternative to ASME B&PV Code Section XI Requirements Re Actions to Be Taken Upon Detecting Leakage at Bolted Connection ML20198B8641998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for TMI-1.With ML20195C6921998-11-12012 November 1998 Safety Evaluation Supporting Amend 52 to License DPR-73 ML20195J8591998-11-12012 November 1998 Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan ML20196B7191998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for TMI-1.With ML20203G1211998-10-30030 October 1998 Informs Commission About Staff Preliminary Views Concerning Whether Proposed Purchase of TMI-1,by Amergen,Inc,Would Cause Commission to Know or Have Reason to Believe That License for TMI-1 Would Be Controlled by Foreign Govt ML20155E7511998-10-15015 October 1998 Rev 1 to Form NIS-1 Owners Data Rept for Isi,Rept on 1997 Outage 12R EC Exams of TMI-1 OTSG Tubing ML20154L5541998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for TMI Unit 1.With ML20153A9941998-09-16016 September 1998 Safety Evaluation Denying Request to Remove Missile Shields from Plant Design ML20151U8821998-09-0808 September 1998 SER on Revised Emergency Action Levels for Gpu Nuclear,Inc, Three Mile Island Nuclear Plant Units 1 & 2 ML20151V2811998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Tmi,Unit 1.With ML20237A8331998-08-12012 August 1998 Safety Evaluation Accepting USI A-46 Program Implementation at Plant,Unit 1 ML20237C6411998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Tmi,Unit 1 ML20236R2201998-06-30030 June 1998 Monthly Operating Rept for June 1998 for TMI-1 ML20236W9961998-06-0909 June 1998 1998 Quadrennial Simulator Certification Rept ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20249A1061998-05-31031 May 1998 Monthly Operating Rept for May 1998 for TMI-1 ML20247G0761998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Three Mile Island Nuclear Station,Unit 1 ML20212A2191998-04-22022 April 1998 Rev 3 to Gpu Nuclear Post-Defueling Monitored Storage QAP for Three Mile Island Unit 2 ML20248H6991998-04-0808 April 1998 Requests,By Negative Consent,Commission Approval of Intent to Inform Doe,Idaho Operations Ofc of Finding That Adequate Safety Basis Support Granting Exemption to 10CFR72 Seismic Design Requirement for ISFSI to Store TMI-2 Fuel Debris ML20216K1061998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Three Mile Island Nuclear Station,Unit 1 ML20217E0811998-03-24024 March 1998 Rev 0 to TR-121, TMI-1 Control Room Habitability for Max Hypothetical Accident ML20212E2291998-03-0404 March 1998 Rev 11 to 1000-PLN-7200,01, Gpu Nuclear Operational QAP, Consisting of Revised Pages & Pages for Which Pagination Affected ML20216F0981998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Three Mile Island Nuclear Station,Unit 1 ML20202F8121998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for TMI Nuclear Station, Unit 1 ML20199G8371998-01-22022 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Three Mile Island Nuclear Station,Unit 1 ML20198N2901998-01-12012 January 1998 Form NIS-1 Owners' Data Rept for Isi ML20199J3251997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Three Mile Island Nuclear Station,Unit 1 1999-09-30 |
Text
GPU Nuclear Corporation 3J Nuclear =ggsfg8o 8 Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer's Direct Dial Number:
717-948-8005 3200-83-544 November 15, 1983 Dr. T. E. Murley, Regional Administrator U. S. Nuclear Regulatory Commission Region I 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 83-044 This telecopy is to confirm the conversation between Mr. R. Conte, NRC Senior Resident Inspector and Mr. M. Nelson, PRG Chairman, at 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> on November 14, 1983.
l During a site walkdown by the Architect-Engineer, redundant circuits (RU-489 and RU-490) in the Emergency Feedwater auto initiation circuitry were found to be installed / routed in the same cable bundle and thus do not meet separation criteria for safety grade circuits. Since GPUN had previously notified the NRC that this circuitry had been upgraded to safety grade, this event is considered reportable under Technical Specification 6.9.2. A.9.
These cables will be separated to meet the applicable criteria in January, 1984. Further details will be provided in the 14 day followup report.
Si, erely, 0312010028 831135 i PDR ADOCK 05000289 3 S PDR R. J. Toole Operations and Maintenance Director, TMI-1 cc: R. Conte CARIRS GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation 6
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