ML19270H515
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| ML19270H515 | |
| Person / Time | |
|---|---|
| Site: | Three Mile Island  |
| Issue date: | 04/04/1974 |
| From: | John Miller METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19270H513 | List: |
| References | |
| NUDOCS 7910260704 | |
| Download: ML19270H515 (1) | |
Similar Documents at Three Mile Island | |
|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20211M6491997-10-0808 October 1997
[Table view]Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20056E9751993-08-19019 August 1993 Provides Insp Results & Safety Analysis Re Operational Amplifiers Discussed in 920917 & 23 Ltrs as Potential Safety Issue.Concludes That There Are No Safety Concerns W/Respect to Buffer Amplier Module.Ltr Not 10CFR21 Notification ML20044G5311993-05-26026 May 1993 Suppl to 921207 Part 21 Rept Re Declutch Sys Anomaly in Certain Types of Valve Actuators Supplied by Limitorque Corp.Limitorque Designed New Declutch Lever Which Will Be Available in First Quarter 1993 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20118B2191992-09-23023 September 1992 Suppl to Part 21 Rept Re Potential Deviation in Some Bailey Controls Co 88 Series Modules,Transmitted Via .One Module Found Incapable of Reaching 100% Output at Max Rated Load.Recommends That Circuit Board Assemblies Be Inspected ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML17262A2621990-11-30030 November 1990 Part 21 Rept Re Chilled Water Sys.Initially Reported on 901030.Evaluation of Perry Plant Will Be Sent by 901230 ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20245D9541988-09-0606 September 1988 Part 21 Rept Re Condition Involving Inconel 600 Matl Used to Fabricate Steam Generator Tube Plugs & Found to Possess Microstructure Susceptible to Stress Corrosion Cracking ML20203D0221986-07-14014 July 1986 Part 21 Rept Re Air Monitoring Sys Probes Exhibiting Blue Tip Rather than Normal White Tip & Insensitive to Chlorine. Caused by Improper Handling/Storage.Advisory Bulletin Encl. Item Not Reportable Per Part 21 NRC-86-3142, Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List1986-06-19019 June 1986 Part 21 Rept Re Increased Failure Probability of Coils Used in Class 1E Motor Starters & Contactors Supplied to Nuclear Power Plants by Westinghouse.Replacement Coils Mfg for All Starters & Contactors on Encl List ML20134Q1741985-08-29029 August 1985 Part 21 Rept Re Potential Maint Issues Associated w/Anker-Holth Snubbers.Owners of Anker-Holth Snubbers Will Be Informed of Problems & Sent Revs to Technical Instruction Manuals to Include Procedures for Seal & Fluid Maint ML20210G9921985-08-13013 August 1985 Part 21 Rept Re Failure of Isolated Worm Shaft Gear When Certain Critical Speeds Combined W/Repetitive Transfer of Actuator Clutch Mechanism from Manual (Handwheel) to Motor Drive Mode.Two Possible Solutions Noted ML20126C6901985-06-0505 June 1985 Part 21 Rept Re Generator Failure.Concurs W/Encl Louis Allis That Interpolar Connectors Be Removed ML20129G4401985-05-29029 May 1985 Part 21 Rept Re Failure of Inner Polar Connector Between Damper Bar Circuit on Generator Main Field.Cause of Failure Not Defined.Further Investigation Necessary ML20010G6821981-09-16016 September 1981 Part 21 Rept Re Heating, Ventilation & Air Conditioning Ductwork.New Design Info Shows Ducts Could Collapse If Subjected to High Negative Pressure Due to Dirty Filters. Stiffener Angles Will Be Added ML20010C6881981-08-0606 August 1981 Interim Deficiency Rept Re Potentially Reportable Diesel Generator Starting Air Sys Design,Initially Reported 810803. Generator Supplier Will Be Contacted to Determine Whether Deficiency Exists.Problem Suspected to Be Generic in Nature ML20002D5621981-01-13013 January 1981 Interim Deficiency Rept Re Electrical Component Cabinets Where Frame Is Welded to Embedded Steel Angles,Initially Reported 810109.Concrete Failure & Loss of Positive Anchorage Possible.Review Will Be Completed by 810306 ML17266A3591980-10-31031 October 1980 Final Deficiency Rept Originally Reported on 800325 Re Defective Hydramotor Actuators for Dampers & Louvers.Caused by Mfg from Incorrect Matl.Dampers Reworked & Retested. Dampers & Louvers to Be Tested in Preoperational Program ML20085A4831979-12-13013 December 1979 Part 21 Rept Re Visual Linear Defects in ASME III Class 2 Core Flooding Sys Isolation Valve & Unacceptable Indications in Six ASME III Class 1 Decay Heat Sys Isolation Valves at Wppss.Cause Will Be Investigated ML20090F4011977-10-11011 October 1977 Part 21 Rept Re Defective Auxiliary Feed Pump Governor. Initially Reported on 770930.Governor Modified at Woodward Governor Co Facilities ML19319C8951974-10-0303 October 1974 Deficiency Rept Re Internals Handling Fixture Spherical Nut Retaining Device Potential to Become Unthreaded.Caused by Design Error.Capture Device Redesigned & Hole Drilled in Threaded Rod to Ensure Capture by Set Screw ML19262A3091974-04-26026 April 1974 Deficiency Rept Re 3/4 Inch Carbon Steel Nut Discovered on Top of Lower Grid Assembly at Interface of Core Positions L-2 & M-3.Found During post-hot Functional Insp of Reactor Internals.Addl Insps & Investigations in Progress ML19270H5161974-04-11011 April 1974 Deficiency Rept Re Buckling Inward of Upper Section of Sodium Thiosulfate Tank While Filling Tank.Caused by Negative Internal Pressures.Procedure for Establishing Geometry of Buckled Tank Plate Being Developed ML19270H5151974-04-0404 April 1974 Deficiency Rept Re Failure of Diesel Generators to Operate When Given Start Signal During Engineered Safeguards Surveillance Tests.Applicable Procedures Being Revised & Review Conducted of Safeguards Test Requirements ML19210B2211974-03-29029 March 1974 Ro:On 740329,nuclear Svc River Water Pump Failed During Hot Functional Test Sequence.Caused by Pump Shaft Fracture in Pump Motor Shaft Coupling Area.Motor & Pump Returned to Respective Vendors for Insp & Repair ML19262A3801974-03-15015 March 1974 Deficiency Rept Re Diaphragm Sucked Over Suction Screen Which Cut Off Flow During Draining of Condensate Storage Tank 1B.Condenser Vacuum Collapsed Suction Screen Which Punctured Diaphragm.New Screen Designed ML19290A4951974-03-0707 March 1974 Deficiency Rept Re Failure of 1B HPI Pump.Caused by Damage to Seal Rings of Two Stages of Pump & Personnel Errors. Repairs to Pump Completed Per Work Request Revision of Administrative Procedure 1012 ML19210B3481974-03-0101 March 1974 Deficiency Rept Re Lack of Separation of Seven Circuits in Vicinity of Heating,Ventilation & Air Conditioning Panel Underneath Control Room Discovered During Jan 1974 Audit by General Public Utils Svc Corp ML19290A4831974-02-22022 February 1974 Final Deficiency Rept Re Revision of Specific Heat Curve for U Oxide Fuel as Utilized in Transient Computer Codes for Plant Safety Analyses.Forwards New Specific Heat Code & LOCA Limited Max Allowable Linear Heat Rate Graphs ML19290A4821974-02-19019 February 1974 Final Deficiency Rept Re Discrepancies Between Physical Cable Count & Cable Tray Loading Summary Quantities.Forwards Table W/Summary & Resolution of Audit Findings.Revised Pull Slips Issued for Circuits CG-415 & RV-844 ML19276H3551974-02-0404 February 1974 Notifies That Reactor Bldg Spray Pump Motors Do Not Meet Design Criteria.Motors Not Able to Reach Normal Operating Speed within Six Seconds Under Worst Undervoltage Condition. No Corrective Action Will Be Taken ML19210B2691973-12-20020 December 1973 Deficiency Rept Re Bent Vent Valve Thermocouple Guide Tubes & Bent Thermocouple Nozzles on Reactor Vessel Closure Head. Caused by Misalignment of Nozzles on Head to Guide Tubes on Plenum.Corrected by Partial Removal of Nozzles ML19210B2571973-12-12012 December 1973 Deficiency Rept Re Discrepancies Between Physical Cable Count & Cable Tray Loading Summary Quantities.Seven of 20 Safeguard Cable Trays Randomly Selected Did Not Agree W/ Summary.Caused by Revised Pull Clips W/Routing Change ML19210B3831973-12-0404 December 1973 Deficiency Rept Re Partial Draining of RCS from 150 Inches to Near 0 Inches Pressurizer Level(Approx 40000 Gallons). Caused by Personnel Error.Operator Closed DH-V6A Valve. Plant Shut Down W/No Testing in Progress ML19290A4881973-11-0909 November 1973 Deficiency Rept Re Failure of Nuclear Svc River Water Pump 1B Motor.Caused by Length of Rope Tangled in Pump.No Immediate Corrective Action Required.Motor Sent to Vendor for Insp & Repair ML19290A4771973-10-0404 October 1973 Deficiency Rept Re Discovery of Limitorque Valve Operators DH-V-6A & BS-V-3B on Floor Removed from Respective Valves & Partially Wetted During 730831 de-energizing of Power to Perform Electrical Changes to TMI-1 Sys ML19210B3921973-09-21021 September 1973 Deficiency Rept Re Arc Suppression Diode Failure in Westinghouse Model DB-25 & DB-50 Breakers During Checkout. Caused by Exposure of Diodes to Voltage Spikes in Excess of Breakdown Voltage,Causing Diodes to Short Out ML19250C1001973-09-18018 September 1973 Deficiency Rept Re Failure of Stems on Core Flood Valves CF-V-1A & CF-V-1B Equipped W/Limitorque SMB-4 Operators. Diameter of Stem Caused Thread to Be Tapered.Stem Nut Would Bind & Prevent Further Opening by Hand Operation ML19290A4981973-08-20020 August 1973 Deficiency Rept Re Seismic I Hanging Conduit Lacking Appropriately Approved Detail Per Recent Audit.Addl Info Required for Approval Not Sent.Criteria & Drawings Will Be Prepared to Prevent Further Occurrences ML19290A4721973-08-20020 August 1973 Deficiency Rept:On 730515 Nuclear Svc River Water Pump 1C Motor Caught Fire & Supply Breaker Tripped During Operation Supporting Testing of Circulating Water Sys.On 730717 Knocking Noise & Burning Odor Emanated from Pump ML19290A4731973-08-17017 August 1973 Deficiency Rept Re Grease Leakage Discovered on 730720 from 2090P Casing Filler Mfg by Viscosity Oil Co Into Vertical Tendon Conduits.Liner Plate Checked & No Bulging or Buckling Found.Samples of Leaking Matl Taken ML19290A4631973-08-0606 August 1973 Deficiency Rept Re Apparent Breakdown in QA Program Including Insp & Testing of Protective Electrical Equipment & Circuitry.Qc Surveillance of Multi-Amp Engineering Svcs Reinstituted & Notification Procedures Begun ML19290A4551973-07-12012 July 1973 Final Deficiency Rept Re Completion of Valve Wall Thickness Verification Program.Wall Thickness of Valves Adequate. Records of Measurements & Evaluations Available at Site ML19290A4431973-06-0404 June 1973 Final Deficiency Rept Re Scratches Observed on 730514 at Eight Locations Around Top Outer Surface of Reactor Vessel Internal Thermal Shield After Removal of Lower Core Support Assembly Shipping Container ML19290A4271972-12-0808 December 1972 Deficiency Rept Re Anomalous Conditions in Seven Shop Welds During Pre Baseline Inservice Insp.All Are B&W Shop Welds. Submits Findings of B&W Nov 1972 Ultrasonic Testing of Specified Welds.Plans Further Exploratory Testing 1997-10-08 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 |
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/ METROPOLITAN EDISON COMPANY ._ ~<accrecmsvooono. a:we 07r CFFICE BOX 542 READING. PENNSYLVANI A 19603 TELEPHONE 215 - 929G601 April 4, 1974 Dr. D. F. Knuth, Director Directorate of Regulatory Operations Office of Regulation U.S. Atomic Energy Comission Washington, DC 20545
Dear Dr. Knuth:
SUBJECT:
THREE IfILE ISLAND NUCLEAR STATION UNIT 1 DOCKET N0. 50-289 DIESEL GENERATORS You were notified on March 4, 1974, of a situation which =ay be considered reportable under 10 CFR 50.55(e), " Conditions of Construction".
This situation related to the Diesel Generators.
The Diesel engines had been warmed and manually shut down in preparation for surveillance tests. This action energizes and seals in the automatic shutdown relay. During engineered safeguards surveillance tests, the diesel generators failed to run when given a start signal.
Investigation of the engineered safeguards test logic revealed that one test channel (one of two) does not override the shutdown relay, whereas the second channel, or an actual safeguards sian do override this relay.
This was the reason for the failure to start.
The applicable procedures are being revised to sequence the pre-parations and test steps to assure proper checking of the safecuards contacts in the Diesel Generator circuitry. Engraved instructions have been placed at the engines to emphasize the operational requirements to assure the diesel generators are reset properly.
Additionally, the design agent is conducting a separate review of the safeguards test requirements relative to the diesel generator circuit logic. The results of this review will be available for your review at the Three Mile Island site.
t 7
Very truly yours, y W y . C. Miller Vice President asb
$910260 Ch
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