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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000331/LER-1993-0061993-09-0909 September 1993 LER 93-006-00:on 930813,partial PCIS Group 3 Isolation Occurred Due to Inadequate Written & Verbal Communications. Event Will Be Reviewed by Engineering,Operations & Maint by 931201 to Stress Need for Good communications.W/930909 Ltr ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000331/LER-1983-027, /01T-0:on 830803,during Surveillance Required by Inoperable RCIC (LER 83-027),speed Indication for HPCI Turbine Failed.Caused by Faulty Turbine Magnetic Speed Pickup.Turbine Oil Sys Adjusted1983-08-17017 August 1983 /01T-0:on 830803,during Surveillance Required by Inoperable RCIC (LER 83-027),speed Indication for HPCI Turbine Failed.Caused by Faulty Turbine Magnetic Speed Pickup.Turbine Oil Sys Adjusted 05000331/LER-1981-016, Updated LER 81-016/01T-1:on 810421,lower Crankshaft Thrust Bearing 13 & Adjacent Bearing 12 Found Wiped on Journal Surface.Caused by High Temp.Crankshaft Thrust Bearings Replaced & Crankshaft Relapped1983-05-16016 May 1983 Updated LER 81-016/01T-1:on 810421,lower Crankshaft Thrust Bearing 13 & Adjacent Bearing 12 Found Wiped on Journal Surface.Caused by High Temp.Crankshaft Thrust Bearings Replaced & Crankshaft Relapped 05000331/LER-1981-015, Updated LER 81-015/01T-1:on 810421,lower Crankshaft 14 Bearing Found Wiped on Journal Surface Similar to Problem Identified on Diesel 1G-31.Caused by High Temp.Bearing Replaced & Crankshaft Relapped1983-05-16016 May 1983 Updated LER 81-015/01T-1:on 810421,lower Crankshaft 14 Bearing Found Wiped on Journal Surface Similar to Problem Identified on Diesel 1G-31.Caused by High Temp.Bearing Replaced & Crankshaft Relapped ML20148N5821978-06-30030 June 1978 /01T-0 on 780617:water Leak Found in Area of B Recirculation Sys N2A Inlet Nozzle Caused by Wall Crack in Nozzle Safe End.Lab Analysis Will Be Performed to Determine Cause of Cracking 1993-09-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H8991999-10-18018 October 1999 SER Approving Licensee Requests for Relief NDE-R001 (Part a & B),NDE-R027,NDE-028,NDE-R029,NDE-R030,NDE-R032 & NDE-R035. Relief Request NDE-036,denied & Relief Request NDE-R-034, Deemed Unnecessary NG-99-1415, Monthly Operating Rept for Sept 1999 for Daec.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Daec.With ML20212H2381999-09-22022 September 1999 Safety Evaluation Supporting Amend 228 to License DPR-49 NG-99-1226, Monthly Operating Rept for Aug 1999 for Duane Arnold Energy Center.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Duane Arnold Energy Center.With NG-99-1115, Monthly Operating Rept for July 1999 for Daec.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Daec.With NG-99-0963, Monthly Operating Rept for June 1999 for Daec.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Daec.With ML20195G9901999-06-0909 June 1999 Safety Evaluation Supporting Amend 227 to License DPR-49 NG-99-0835, Monthly Operating Rept for May 1999 for Daec.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Daec.With ML20206N7551999-05-13013 May 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safey-Related Power-Operated Gate Valves NG-99-0682, Monthly Operating Rept for Apr 1999 for Duane Arnold Energy Center.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Duane Arnold Energy Center.With NG-99-0530, Monthly Operating Rept for Mar 1999 for Daec.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Daec.With ML20207G0251999-03-0303 March 1999 SER Concluding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety- Related MOVs at Duane Arnold & That Licensee Adequately Addressed Actions Requested in GL 96-05 NG-99-0330, Monthly Operating Rept for Feb 1999 for Daec.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Daec.With ML20202B4311999-01-26026 January 1999 Safety Evaluation Accepting Request for Approval to Use ASME Code Case N-508-1 in ISI Program for Duane Arnold Energy Ctr ML20202B3851999-01-26026 January 1999 Safety Evaluation Addressing Thermo-Lag Related Ampacity Derating Issues.Ampacity Derating Analysis Results Acceptable NG-99-0020, Monthly Operating Rept for Dec 1998 for Daec.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Daec.With ML20206N3211998-12-0707 December 1998 Final Part 21 Rept Re Piston Failure of MSIV Actuator at Daec.Rept Indicates That No Reportable Defect Exists,Per 10CFR21 NG-98-2010, Monthly Operating Rept for Nov 1998 for Daec.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Daec.With ML20196F9571998-11-24024 November 1998 Rev 20 to QA Program Description,Ufsar 17.2 for Daec NG-98-1875, Monthly Operating Rept for Oct 1998 for Daec.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Daec.With NG-98-1717, Monthly Operating Rept for Sept 1998 for Daec.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Daec.With NG-98-1767, Cyclic Rept of Facility Changes,Tests & Experiments,Fire Plan & Commitment Changes,For Period from 970301-980930. with1998-09-30030 September 1998 Cyclic Rept of Facility Changes,Tests & Experiments,Fire Plan & Commitment Changes,For Period from 970301-980930. with ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML20153B4141998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for DAEC NG-98-1389, Monthly Operating Rept for July 1998 for DAEC1998-07-31031 July 1998 Monthly Operating Rept for July 1998 for DAEC ML20236X5321998-07-29029 July 1998 Safety Evaluation Re USI A-46 Program Implementation for Plant ML20236W0021998-07-29029 July 1998 Safety Evaluation Accepting Request for Relief NDE-R020 Re Third 10-yr ISI Interval of Plant,Per 10CFR50.55a(a)(3(i) ML20236S2541998-07-14014 July 1998 Special Rept 98-01:on 980629,diesel-driven Fire Pump Was Inoperable for Greater than Seven Days.Caused by Sheared Off Tie Rods on Accessory Drive End of Engine.Evaluated Condition,Procured Parts & Replaced Tie Rods ML20236R3251998-06-30030 June 1998 Monthly Operating Rept for June 1998 for DAEC ML20249B5171998-05-31031 May 1998 Monthly Operating Rept for May 1998 for DAEC ML20247P5651998-05-18018 May 1998 Part 21 Rept Re Model SA-A101 MSIV A' Actuator Showing Evidence of Internal Leakage,In Both Directions Past Pneumatic Piston.Situation Being Reviewed to Determine If Failure Could Pose Substantial Safety Hazard ML20247K1881998-05-0808 May 1998 Rev 0 to Cycle 16 COLR, for May 1998 ML20247H9381998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for DAEC ML20216J9171998-04-16016 April 1998 Safety Evaluation Accepting Relief Request MC-R001 for First 10-yr Interval of Containment Insp Program Per 10CFR50.55a (a)(3)(ii),per 971219 Request ML20217K7251998-04-16016 April 1998 Correction to SE of Relief Request MC-R001 Re Qualification Requirements for non-destructive Exam Personnel Performing Containment Insp ML20217K0471998-04-0101 April 1998 Safety Evaluation Authorizing Proposed Alternative in Relief Request NDE-R004 for Plant Third 10-yr ISI Interval,Based on Finding That Compliance W/Code Would Result in Hardship W/O Compensating Increase in Level of Quality & Safety ML20217H8831998-04-0101 April 1998 Safety Evaluation Supporting Request for Relief for Third ISI Program NG-98-0650, Monthly Operating Rept for Mar 1998 for Duane Arnold Energy Center1998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Duane Arnold Energy Center ML20216F6791998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for DAEC ML20217F8841998-03-23023 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Program Plan Requests for Relief for Plant NG-98-0398, Monthly Operating Rept for Feb 1998 for DAEC1998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for DAEC NG-98-0252, Monthly Operating Rept for Jan 1998 for Duane Arnold Energy Center1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Duane Arnold Energy Center ML20199L3481998-01-31031 January 1998 Rev 0 to Duane Arnold Energy Ctr Emergency Action Level (EAL) Technical Basis Document ML20249B3331997-12-31031 December 1997 1997 Annual Rept for Alliant Corporation ML20249B3391997-12-31031 December 1997 Central Iowa Power Coopertive 1997 Annual Rept ML20249B3351997-12-31031 December 1997 1997 Annual Rept for Corn Belt Power Cooperative NG-98-0017, Monthly Operating Rept for Dec 1997 for Duane Arnold Energy Center1997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Duane Arnold Energy Center NG-97-2118, Monthly Operating Rept for Nov 1997 for DAEC1997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for DAEC ML20199J6841997-11-21021 November 1997 SER Approving Relief Requests to Second 10-year Inservice Inspection Interval for Duane Arnold Energy Center NG-97-1959, Monthly Operating Rept for Oct 1997 for DAEC1997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for DAEC 1999-09-30
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. F**lE ARNOLD CLERGY CZirzER *
- Icma Electric Light and Power Company LICENSEE EVCIT REPORT-Supplemental Data
.. Docket Number 030-0331 ,
t.icancoa Event Report Date: 063078 . .
Reportable Occurrence No: 78-030 Event Description -
On June 17, 1978 during weekly control valve testing an automa' tic reactor scram occurred due to reactor protection system relay problems (see R0 78-031) and the CV l I
testing.* After the plant was shutdown a drywell inspectior, was made to detemine the source of drywell unidentified leak of 3 GPM. Technical Specification 3.6-C limits unidentified leakage into the primary gantainment to 5 GPM. Water was found leaking from the shield blocks around the "B" recirculation system N2A inlet nozzle. The '
reactor was placed in a cold shutdown condition and the shield blocks removed for further inspection of the nozzle area. The . leakage was found to be the result of a through wall crack in the nozzle safe end approximately 4 to 6 inches in circumferential length. ,
Ultrasonic testing and radiographic examination were then begun to detemine the full extent of the cracking in the N2A nozzle safe end and to check for similar problems in the remaining 7 nozzle safe ends. The examinations revealed suspect indications in 5 other safe ends, none of which were through wall cracks. The remaining 2 nozzle safe ends had no suspect indications. Primary system structural integrity requirements are listed in Technical Specifications Section 3.6-G.
Causa Description _
The exact cause of the cracking has not been determined. Following removal, a laboratory analysis will be done on a cracked safe end to determine the failure mechanism. ,
Corrective Action ,
Current plans are to replace all eight safe ends with new safe ends of an improved design.
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