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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
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- ',,. UNITED STATES I; g NUCLEAR REGULATORY COMMISSION 4 "
.5 l WASHINGTON. D, C. 20555 JUN 161989 L C. J. Lovell EG&G Idaho, Inc.
MS 2407 P.' O. Box 1625 Idaho Falls, ID 83415-2407 W. P. Poore Nuclear Operations Analysis Center .
Building 9201-3 MS-8065 Oak Ridge National Laboratory P. O. Box 2009 Oak Ridge, TN 37831 RESOLUTION OF LERs MISSING FROM LERTRK/SCSS/DCS Ref: Letter from C. J. Lovell to W. P. Poore, First Ouarter 1989 LERTRK/SCSS Ouality Assurance Check - CJL-5-89, April 20,1989.
The referenced letter contained a listing of sequence numbers of Licensee Event Reports (LERs) that were missing form the 1988 INEL datafile, SCSS, and NRC DCS. I have reviewed this list and have been able to resolve all of the missing items.
Several of the LERs had been issued but somehow never got into the NRC document system for distribution and inclusion onto DCS. Copies of these LERs are enclosed. They include the following event reports:
LERs THAT HAVE BEEN ISSUED AND ARE ENCLOSED 25488011 33888021 26588010 41288018 26588022 41488002 27588029 41488004 30488015 Some of the missing reports have just been issucd. They have been received and distributed by the NRC. Copies of these LERs are not enclosed. They include:
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LERs THAT HAVE JUST BEEN RECEIVED UNDER NORMAL DCS DISTRIBUTION AND ARE NOT ENCLOSED l
27788027 31388023 31388019 35488014 31388020 36888020 31388022 52888023 Another grouping of missing LERs were associated with 50.72 reports which were subsequently determined to not be reportable as 50.73 repons. Instead of reassigning the LER number to a reponable event, the licensees simply cancelled the report and did not ,
reuse the sequence number. The cancelled sequence numbers include:
LERs THAT WERE CANCELLED AND WILL NOT BE ISSUED 21988025 33188014 21988032 34488034 25088031 34488038 28088047 34488048 28288012 41288014 N 32388017 52988016 Finally, two special cases were discovered. These involved H. B. Robinson and Browns Ferry. Discussions of these cases follow.
SPECIAL CASES i
H. B. Robinson 2 handles their secur.ty event repons differently than other licensees. In J their case, they issue their security event mpons on an LER form but the number assigned j on the form is a sequence series that begins with an S (e.g., 88-S01, 88-S02). This method is in agreement with all other licensees. However, H.B. Robinson also assigns a )
standard LER sequence number to these security event repons. This sequence number is assigned and tracked internally and is only included, if at all, for information on the ,
transmittal letter of the security event repon. Thus, only persons who received security l event reports from the DCS would know about these corresponding regular sequence l numbers. For 1988, H. B. Robinson issued five such security repons, numbers S01 l through S05. The normal LER sequence number assigned to these repons are as follows:
H. B. ROBINSON SECURITY REPORT /LER SEQUENCE NUMBERS S01 26188004 SO2 26188016 S03 26188025 SO4 26188029 S05 26188030 2
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Browns Ferry issued LER 26088050. Previous discussions with the licensee indicated that i this number was in error in that it was truly a Unit 2 event but the sequence number given was for Unit 1. To correct this error, a revision would be forthcoming rr, assigning this LER as 26088019. This revision has yet to be received. I contacted the licensee again and was informed that 26088019 is still to be issued but extensive reanalysis of corrective actions which will be incorporated into the LER have yet to be completed. No firm date ,
of issuance could therefore be given. In addition, it wt.s noted that the original transmittal 1 letter for this revision would indicate that LER number 25988050 would not be used. 1 l
Thus, LER 25988050 should be listed as being "Not Issued" and, once the revision LER 26088019 is issued, the present hole of LERs from 26088019 thmugh 26088049 should be removed with LER 28088019 being the final LER in numeric sequence for Unit 2.
Based on there clarifications, the highest LER sequence number that will be used in 1988 :
at each of the plants is listed in the table on the following page. Both LERTRK and the inventory file for SCSS should ccutain information pertinent to all report sequence numbers from 88001 through these highest numbers. As always, additional LERs may subsequently be submitted, but their sequence numbers should only add to this listing. i If you have any questions, please contact me.
Sincerely,
/YMwbY Thomas R. Wolf enclosure cc w/ enclosure NRC Document Control Branch cc w/o enclosure RLDennig JLCrooks MHWilliams JCRosenthal WBuchanan ETLaats 3 )
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q HIGHEST LER SEQUENCE NUMBER 02988015 27888011 32488021 38888016 13388002 28088048 32588035 38988004 15588009 28188025 32788047 39588015 20688021- 28288013 32888041 39788038 21388023 28588038 33188019 40088035 21988035 28688010' 33388014 40988002 22088021 28788006 33488016 41088068 13788023 28988006 33588008 41288020 24488010 29388027 33688011 41388027 24588013 29588024 33888028 41488033 24788020 .29688008 33988019 -41688020 24988018 29888027 34188037 42388028 25088032 -30188003 34488049 42488045 25188012 30288028 34688029 44088047 25488016 30488018 34888024 44388010 25588025 30588013 35288043 45488011 25988053 30688002 35488036 45588012 26088019' 30988011 36188036 45688026 261880302 31188026 36288012 45788032 26388008 31288021 36488010 45888029 26588030 31388025 36688025 46188032 26688010 31588014 36888022' 48288029 26788018 31688011 36988049' 48388015 26988014 31788015 37088013 49888066
- 27088003 31888006 37388029 49988001 27188015 32088011 37488017 52888026 27288020 32188019' 38288034 52988017 27588032 32288019 38788024- 53088008 27788033 32388026 8 See "Special Case" discussion on Browns Ferry. Assumes LER 26088050 will be reissued as 26088019.
2 See "Special Case" discussion on H. B. Robinson.
5 Indian Point 3 LER 28688010 is a " Safeguards Event Report" only.
' Reflects recent LERs just received through normal DCS distribution. Copies of these LERs are not included.
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