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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARML20245G9881989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed 05000275/LER-1983-004, Updated LER 83-004/08X-1:on 830419,grinding Wheel & Rotary File Gouges Discovered on Main Coolant Sys Piping on Discharge Side of Main Coolant Pump 3.Gouges Intentionally Caused by Unknown Persons.Gouges repaired.W/840117 Ltr1984-01-17017 January 1984 Updated LER 83-004/08X-1:on 830419,grinding Wheel & Rotary File Gouges Discovered on Main Coolant Sys Piping on Discharge Side of Main Coolant Pump 3.Gouges Intentionally Caused by Unknown Persons.Gouges repaired.W/840117 Ltr 05000275/LER-1983-014, Updated LER 83-014/01T-1:on 830526,torque Switch Binding Observed During Maint on Limitorque Operator.Caused by Excessive Size of Mounting Screw Heads.Screws Replaced1983-11-0101 November 1983 Updated LER 83-014/01T-1:on 830526,torque Switch Binding Observed During Maint on Limitorque Operator.Caused by Excessive Size of Mounting Screw Heads.Screws Replaced 05000275/LER-1983-006, Updated LER 83-006/01T-1:on 830510,possible Undersize Condition Discovered on Reactor Coolant Piping Weld WIB-RC-2-17 During Ultrasonic Testing.Weld Confirmed to Be Above Min Wall Requirements Mechanically1983-10-13013 October 1983 Updated LER 83-006/01T-1:on 830510,possible Undersize Condition Discovered on Reactor Coolant Piping Weld WIB-RC-2-17 During Ultrasonic Testing.Weld Confirmed to Be Above Min Wall Requirements Mechanically 05000275/LER-1983-007, Updated LER 83-007/01T-1:on 830509,during Welding of Reinforcement Pad on Branch Connection to Loop C Component Cooling Water Sys,Water Leaked from Weld Area.Caused by Grinding on Fillet Overweld.Overweld Removed1983-09-26026 September 1983 Updated LER 83-007/01T-1:on 830509,during Welding of Reinforcement Pad on Branch Connection to Loop C Component Cooling Water Sys,Water Leaked from Weld Area.Caused by Grinding on Fillet Overweld.Overweld Removed 1989-06-16
[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] |
LER-2083-006, Updated LER 83-006/01T-1:on 830510,possible Undersize Condition Discovered on Reactor Coolant Piping Weld WIB-RC-2-17 During Ultrasonic Testing.Weld Confirmed to Be Above Min Wall Requirements Mechanically |
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. URMTE GSEMRT - PREVIOUS REPORT'OATE 05/23/83 PeTic FDGM 366 U.S. .sutLSAR RStubATSRY Cf Ma%ggse K.PP *i3VED OY C MfJ S#',Mso e LICENSEE EVENT REPORT 8'S W i e CONT;tOL 8 LOCK: l l l l l l l@ (PLEASE PAINT GR TYPE ALL REQUIRED INFURMATIT.N) l ali ll. .Cl AlD lC l P l l l@l 010 l- 1010 m.......... .. .. m...........
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EVENT DESCRIPTION AND PROSA8LE CONSEQUENCES h I o l2 l l Prior to fuel load, ultrasonic (UT) thickness measurements woro taken on I lo ja l l reactor coolant piping welds to establish baseline data for subsequent NDE inspec- l l a l, l l tions. During these examinations, a possible under size condition was discovered l l o is l l on weld WIB-RC-2-17. Minimum wall thickness by UT measurement indicated that the l l o }6 l l Weld was 0.065 inches below the required thickness of 2.215 inches. Reportable l j o l 7 l l p'er Technical Specification Section G.9.1.12.i . This event has in no way affected l 1 o 18 l l the public's health and safety. l
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CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS 27 l i lo l l This is a final report. Analysi, has shown that UT measurements lack the l lilt ll precision to accurately determine the wall thicknes; of reactor coolant piping weldf lila l l Each weld initially determined to be undersized ba:,ed on UT measurements was l l ils l l confirmed by mechanical measurements to actually be above minimum wall l liI4ll requirements.
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~ ef ATTAC MENT TO LER 83-006/01T-1 i
PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON, UNIT 1 DOCKET NO. 50-275 SUPPLEMENTAL INFORMATION Preliminary measurements obtained during the performance of a Non-Section XI Code ultrasonic thickness testing indicated that a pipe to pipe weld in Reactor Coolant Loop No. 2 between the Reactor Pressure Vessel and the Reactor Coolant Pump may have been less than the design minimum wall thickness of 2.215 inches.
!- A full investigation was. conducted and a report made to the NRC entitled,
" Pacific. Gas and Electric Company's Report on Investigation of Reactor Coolant Pipe Weld Thickness at Diablo Canyon," dated July 1,1983. The report concluded that the latest state-of-the-art ultrasonic measurement techniques
- cannot be utilized for precise thickness measurements of stainless steel piping welds which are greater than two (2) inches thick. A full review of 4
quality records and numerous mechanical measurements determined that all reactor coolant piping welds-are above the design minimum wall thickness requirements.
s 1
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PACIFIC OAS AND ELECTR,IC C O M PANY PGtNf3 l 77 BEALE STREET SAN FRANCISCO, CALIFORNIA 94106. (415) 781-4211. TWX 910 372-6587 JAMES D SHIFFER $,,g,,
DEPARTMENT OF NUCLEAR PLANT OPERATIONS NUCLEAR POWER GENERATION
} { :f '<.r 4l 130 [ 9 Q'n D October 13, 1983 Mr. John B. Martin, Regional Administrator U. S. Nuclear Regulatory Consnission, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596-5368 Re: Docket No. 50-275, OL-DPR-76 Diablo Canyon Unit 1 Licensee Event Report 83-006/01T-1 Weld in Reactor Ccclant Loop No. 2
Dear Mr. Martin:
Pursuant to Section 6.9.1.12.i of the Technical Specifications, Appendix A to the Diablo Canyon Unit 1 Operating License, enclosed is a revision to the subject Licensee Event Report containing updated information on welds in the. Reactor Coolant system which were suspected of being below the minimum wall thickness requirements.
This event has in no way affected the public's health and safety.
Sincerely,
~
t.n p Enclosure cc: G. W. Knighton Director, Office of Management Information and Program Control Service List i
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05000275/LER-1983-001, Forwards LER 83-001/03L-0 | Forwards LER 83-001/03L-0 | | 05000275/LER-1983-002, Forwards LER 83-002/03L-0 | Forwards LER 83-002/03L-0 | | 05000275/LER-1983-004, Updated LER 83-004/08X-1:on 830419,grinding Wheel & Rotary File Gouges Discovered on Main Coolant Sys Piping on Discharge Side of Main Coolant Pump 3.Gouges Intentionally Caused by Unknown Persons.Gouges repaired.W/840117 Ltr | Updated LER 83-004/08X-1:on 830419,grinding Wheel & Rotary File Gouges Discovered on Main Coolant Sys Piping on Discharge Side of Main Coolant Pump 3.Gouges Intentionally Caused by Unknown Persons.Gouges repaired.W/840117 Ltr | | 05000275/LER-1983-006, Updated LER 83-006/01T-1:on 830510,possible Undersize Condition Discovered on Reactor Coolant Piping Weld WIB-RC-2-17 During Ultrasonic Testing.Weld Confirmed to Be Above Min Wall Requirements Mechanically | Updated LER 83-006/01T-1:on 830510,possible Undersize Condition Discovered on Reactor Coolant Piping Weld WIB-RC-2-17 During Ultrasonic Testing.Weld Confirmed to Be Above Min Wall Requirements Mechanically | | 05000275/LER-1983-007, Updated LER 83-007/01T-1:on 830509,during Welding of Reinforcement Pad on Branch Connection to Loop C Component Cooling Water Sys,Water Leaked from Weld Area.Caused by Grinding on Fillet Overweld.Overweld Removed | Updated LER 83-007/01T-1:on 830509,during Welding of Reinforcement Pad on Branch Connection to Loop C Component Cooling Water Sys,Water Leaked from Weld Area.Caused by Grinding on Fillet Overweld.Overweld Removed | | 05000275/LER-1983-014, Updated LER 83-014/01T-1:on 830526,torque Switch Binding Observed During Maint on Limitorque Operator.Caused by Excessive Size of Mounting Screw Heads.Screws Replaced | Updated LER 83-014/01T-1:on 830526,torque Switch Binding Observed During Maint on Limitorque Operator.Caused by Excessive Size of Mounting Screw Heads.Screws Replaced | |
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