ML20092K119
From kanterella
Jump to navigation
Jump to search
| ML20092K119 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 06/25/1984 |
| From: | Mielke F PACIFIC GAS & ELECTRIC CO. |
| To: | Deyoung R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| REF-PT21-84-262-000 PT21-84-262, PT21-84-262-000, NUDOCS 8406280065 | |
| Download: ML20092K119 (1) | |
Similar Documents at Diablo Canyon | |
|---|---|
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17264A9381997-07-10010 July 1997
[Table view]Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures 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 ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms DCL-85-282, Potential Part 21 Problem Re Pipe Clamps Mfg by Natl Valve & Mfg Co Reported to NRC on 850620 by Pacific Scientific Co. Facility Unaffected.No Class 1 Pipe Clamps Mfg by Natl Valve & Mfg Co Used1985-08-29029 August 1985 Potential Part 21 Problem Re Pipe Clamps Mfg by Natl Valve & Mfg Co Reported to NRC on 850620 by Pacific Scientific Co. Facility Unaffected.No Class 1 Pipe Clamps Mfg by Natl Valve & Mfg Co Used DCL-85-074, Final Deficiency Rept Re Cracks in Welds on Pipe Rupture Restraints Made by Pullman Power Products.Unacceptable Welds Repaired or Modified1985-02-22022 February 1985 Final Deficiency Rept Re Cracks in Welds on Pipe Rupture Restraints Made by Pullman Power Products.Unacceptable Welds Repaired or Modified ML20092K1191984-06-25025 June 1984 Part 21 Rept Adivising of Util Search of Records to Determine If Bahnson Co of Winston-Salem,NC Svcs Used by Util,Per Re Bahnson Co HVAC Equipment ML20092D9711984-06-15015 June 1984 Part 21 Rept Re Thermal Nonrepeatability & Other Calibr Errors in Barton Lot 1 Transmitters.Initially Reported on 840615.Transmitter Defects Identified & Expected Error Deviations Calculated.Utils Notified DCL-84-086, Final Deficiency Rept Re Malfunction of Valve Operator Mfg by Limitorque.Initially Reported on 830627.Existing Screws Will Be Replaced on Affected Valves Prior to Fuel Load.Maint Procedures Modified1984-03-0101 March 1984 Final Deficiency Rept Re Malfunction of Valve Operator Mfg by Limitorque.Initially Reported on 830627.Existing Screws Will Be Replaced on Affected Valves Prior to Fuel Load.Maint Procedures Modified DCL-84-007, Final Deficiency Rept Re Containment Spray Initiation Timing.Timer Setting for Starting of Containment Spray Pump Changed from Original FSAR Table 8.3-4 Value to Value of 26 & 22 for Pumps 1 & 2,respectively1984-01-0909 January 1984 Final Deficiency Rept Re Containment Spray Initiation Timing.Timer Setting for Starting of Containment Spray Pump Changed from Original FSAR Table 8.3-4 Value to Value of 26 & 22 for Pumps 1 & 2,respectively ML20082N6431983-11-29029 November 1983 Part 21 Rept Re Detection of Deficiences in Quality Resulting from Fraudulent Actions by Suppliers.Util QA Dept Designed to Aggressively Monitor Supplier Activities ML20082E6581983-11-10010 November 1983 Final Deficiency Rept Re Capstan Spring Tang Cracks in Pacific Scientific Model PSA-3 Snubbers.Three Snubbers Will Be Replaced Prior to Fuel Load ML20081H3331983-10-28028 October 1983 Interim Deficiency Rept Re Three Potentially Defective Pacific Scientific Model PSA-3 Snubbers.Initially Reported on 831012.Next Rept Will Be Submitted in 30 Days ML20072N9891983-07-0808 July 1983 Interim Part 21 Rept Confirming 830705 Telcon Re Anomalies in Artificially Aged Apparatus (Using Ahrrenius Methodology W/Elevated Temp Aging).Deficiency Found During Qualification Testing for IEEE 323-1974.Draft Notices Encl ML20024C3931983-06-27027 June 1983 Interim Deficiency Rept Re Malfunction of Limitorque Valve Operator.Initially Reported on 830526.Investigation Continuing to Confirm Extent of Problem & Determine Corrective Action.Final Rept to Be Submitted by Fuel Load ML20067B1811982-11-0808 November 1982 Final Deficiency Rept Re Water Hammer Phenomenon in Auxiliary Saltwater Sys.Initially Reported on 821008. Isolable Vacuum Breaker Added to Auxiliary Saltwater Sys to Eliminate Water Hammer Effect.Design Change Forthcoming ML20042A5611982-03-16016 March 1982 Interim Deficiency Rept Re Inadequate Design of Sys Contained in Annulus Area of Containment Bldg,Initially Reported 811105.Further Info of Progress Is Identified in Suppls to LER 81-002 ML20039E9411981-12-22022 December 1981 Final Deficiency Rept Re Containment Spray Sys Pipe Supports,Initially Reported 810918.Supports Reviewed, Qualified & Redesigned Per Corrected Support Loads.Changes to Be Completed Prior to Power Ascension ML20038A6871981-11-0505 November 1981 Deficiency Rept Re Design of Sys Contained in Annulus Area of Unit 2 Containment Bldg.Reviewing Affected Areas & Making Necessary Mods ML20010F8451981-08-27027 August 1981 Final Deficiency Rept Re Reactor Protection & Control Equipment,Initially Reported 810728.Addl Instructions Given to Personnel Re Requirements for Authorization of Work & Need for Review of Work Affecting Seismic Qualification ML20004F5801981-06-12012 June 1981 Interim Deficiency Rept Re 120 Volt Ac Vital Power Boards, Originally Reported 810514.Design of Neutral Block Attachments Will Be Modified.Final Rept by 810815 ML20004F7571981-06-12012 June 1981 Interim Deficiency Rept,Originally Reported on 810514,re Design Deficiency in 120 Volt Ac Vital Power Panelboards. Design of Neutral Block Attachment Screws Modified.Final Rept by 810815 ML20086D0231975-01-15015 January 1975 Final Deficiency Rept Re Steam Generator Primary Nozzle safe-ends.Initially Reported on 740329.Indications Removed by Grinding.Cracks Resulted from Intergranular Attack by Corrosive Environ.Corrective Steps Listed ML20086D0281974-08-28028 August 1974 Interim Deficiency Rept Re Exterior Surfaces of Unit 1 Steam Generator Nozzles.Initially Reported on 740424.Final Rept Submission Contingent on Conclusion of Repair Work,Presently Stalled by Series of Strikes ML20086D0461974-04-24024 April 1974 First Deficiency Rept Re Steam Generator Nozzle safe-end Cracking.Program of Exam & Investigation Begun.Cracking Is Superficial Surface Cracking Caused by Corrosive Attack Due to Exposure to Marine Environ.Final Rept Due 740601 ML20086D0751974-02-14014 February 1974 Final Deficiency Rept Re NSSS Primary Loop Piping Welding Discrepancies.Initially Reported on 731024.Unauthorized Departure from Approved Procedures Corrected.Full Insp Revealed No Detrimental Effects ML20086D1001973-10-24024 October 1973 Preliminary Deficiency Rept Re NSSS Primary Loop Pipe Welding.Discrepant Conditions Discovered on 730920.Welding Halted Until Faulty Conditions Corrected.Wismer & Becker & Westinghouse Conducting Investigations ML20086D1831973-08-21021 August 1973 Deficiency Rept Re Failure of Valves Important to Safety to Meet Min Wall Thickness Requirements.Valve Verification Program Underway.Of 97 Valves tested,37 Set Aside for Further Testing.Results of Tests Forthcoming ML20086D1341973-05-31031 May 1973 Deficiency Rept Re Integrity of Thermoplastic Insulation Jacket on 4.16-kV Metalclad Switchgear Bus Bars,Nonvital 12- Kv Metalclad Switchgear Buses & Related Bus Ducts.Insulation Sys Approved for Repairs Meets ANSI Std C-37.20 ML20086D1551972-11-20020 November 1972 Deficiency Rept Re Reinforced Concrete Compartment Walls of Intake Structure.Design of Auxiliary Salt Water Pump Compartments Reviewed for Tsunami Loading.Design Satisfactory 1997-07-10 Category:TEXT-SAFETY REPORT MONTHYEARML20211A9981999-07-12012 July 1999
[Table view]Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 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 ML20141M0471991-12-31031 December 1991 Pge Annual Rept - 1991 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20085D2951991-08-21021 August 1991 Field Exercise Scenario,Aug 1991 ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20065R8731990-11-30030 November 1990 Monthly Operating Repts for Diablo Canyon Units 1 & 2 for Nov 1990 ML20058P5181990-05-11011 May 1990 Accident Sequence Precursor Program Event Analysis 323/87-005 R2, Loss of RHR Cooling Results in Reactor Vessel Bulk Boiling ML20058P5131990-04-0505 April 1990 Accident Sequence Precursor Program Event Analysis 424/PNO-IIT-90-02A, Loop,Diesel Generator Failure & 36 Min Interruption of SDC During Mid-Loop Operation ML20058P5221990-02-0303 February 1990 Accident Sequence Precursor Program Event Analysis Loss of Reactor Protection Sys Bus B Causes Loss of Shutdown Cooling ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20245G9881989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed DCL-89-117, Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 8904181989-04-27027 April 1989 Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 890418 ML20247M6281989-03-31031 March 1989 Nonproprietary Advanced Digital Feedwater Control Sys Median Signal Selector for Diablo Canyon Units 1 & 2 ML20246P4461989-03-23023 March 1989 Corrected Diablo Canyon Power Plant Unit 2 Second Refueling Outage Inservice Insp (ISI) Rept ML20236E0581988-12-31031 December 1988 Pacific Gas & Electric Co Annual Rept 1988 ML20247H0761988-11-30030 November 1988 Vol 1 to Bit Elimination Study for Diablo Canyon Units 1 & 2 ML20205S9071988-10-31031 October 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20206E7181988-05-30030 May 1988 Analysis of Capsule U from PG&E Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20195G3301988-04-30030 April 1988 Corrected Monthly Operating Repts for Apr 1988 for Diablo Canyon ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant 1999-07-12 |
Text
-
PACIFIC GAS AND ELECTR,IC C O M PANY 77 BEALE STREE? = SAN FRANCISCO, CALIFORNIA 94106 + (415) 781-4218 l
FREDE RICK W, MIELME. .JR.
CHAIRM AN Or THE DOARD June 25, 1984 PGandE File 505.1
Reference:
Letter of May 29, 1984 Richard C. Da. Young to Utility CEOs Mr. Richard C. DeYoung Director, Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. DeYoung:
HVAC Equipment Manufactured by the Bahnson Company We are conducting a thorough search of our records to determine if we have ever used the services of the Bahnson Company of Winston-Salem, North Carolina. We are also contacting all contractors who have been involved with the HVAC system at the Diablo Canyon Power Plant to ascertain if they have utilized the services of the Bahnson Company on work performed at Diablo Canyon.
If our investigation identifies that work was performed by Bahnson Company at the Diablo Canyon Po"er Plant, we will promptly notify the NRC and take appropriate action to determine whether the procurement specification was met and if the product was suitable for its intended service.
Sincerely, J
FWM:bkm D 0 25 S- PDR #
_
Retrieved from "https://kanterella.com/w/index.php?title=ML20092K119&oldid=3491916"