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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML17264A9381997-07-10010 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
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
[Table view]
Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999
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
[Table view] |
Text
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November 5, 1981 - .J"a . . . . . .
Mr. R. H. Engelken, Director -
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Office of Inspection and Enforcunent s /y- -'f'i Fi' r,
/ y[[N'! .:R Region V -
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U. S. Nuclear Regulatory Cmmission ['yJ /y'g ' - C
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Walnut Creek, Ca. 94596 2 d{p y s h 'c,7 '
Re: Docket No. 50-323 :-
A^j Diablo Canyon Unit 2 4 NI j sy \ ~
Dear Mr. Engelken:
On Septmber 28, 1981 Ra; ion V was notified of a deficiency reportable under 10 CFR 50.55(e). The report addressed recently discovered deficiencies in the design of systms containMi in the 5tnnulus area of the Diablo Canyon Uni? 2 containment building.
The reportable conditions as identified for Unit 1 (IBt 81-002/OlX-0) may apply to Unit 2.
The potential effect of this error is that sorm design may not be in empliance with Hosgri seismic design criteria. All affected systuis are being reviewed and rmdifications, as necessary, are being made.
We will keep you infomed of air progress.
r Me truly yours,
! c v .
f cc: Mr. Frank J. Miraglia, Jr. , Cl ef, Licensing Branch No. 3
-M6'>-) y Division of Licensing /
Office of Nuclear Reactor Regulation j(0 U. S. Nuclear Regulatory Cmanission Washington, D. C. 20555 cc: Service List 8111160173 811105 PDR ADOCK 05000323 S PDR}}
