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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20236S2541998-07-14014 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 ML20076K6821983-09-0606 September 1983 Ro:On 830904,HPCI Min Flow Return to Torus Line Throttle Valve Found Opening Intermittently.Later,Rcic Outboard Isolation Valve Would Not Close.Causes Not Stated.Limiting Condition for Operation Declared & Orderly Shutdown Begun ML20080Q3831983-08-23023 August 1983 Ro:On 830308,radiographic Exams Conducted on 10 HPCI Turbine Reversing Chambers.Seven Chambers Did Not Meet Augmented Acceptance Criteria.Cracking Caused by Mfg Process & Pressure Pulsing Fatigue ML20076C0011983-08-0303 August 1983 Ro:On 830803,while Performing Periodic Surveillance Testing on RCIC Sys,Discharge Pressure Instrument PI 2506 Displayed Erroneous Indications.Hpci Turbine Speed Indication Failed Downscale During Testing ML20076M9291983-07-12012 July 1983 Ro:On 830712,engineering Calculations Performed During Piping Walkdown Identified 3/4-inch Hle Pipe Exceeded Design Basis Code Allowable Pipe Stress.Design Change Will Be Implemented to Return Line to within Allowable Conditions ML20072A3881983-05-27027 May 1983 Ro:On 830527,both Divs of Hydrogen/Oxygen Analyzers Determined Inoperable.Orderly Shutdown Commenced.On 830527, a Sys Returned to Operable Status ML20074A4761983-05-0606 May 1983 Ro:On 830212,during Type C Local Leak Rate Testing,Two MSIVs Exceeded Tech Specs.Valves Repaired ML20073S1771983-04-26026 April 1983 Ro:While in Cold Shutdown,W/All Rods Inserted,Reactor Mode Moved from Refuel Position to Shutdown Position & a Logic Did Not Trip.Caused by Failure of a Sys Shutdown Scram Reset Interlock.Unit Maintained in Cold Shutdown ML20069D2771982-09-13013 September 1982 Ro:On 820912,during Normal Operation,Hpci Inboard Steam Supply Isolation Valve MOV-2238 Closed Due to False Leakage Signal from Malfunctioning Temp Differential Switch TDS-2260.In Subsequent Testing,Hpci fast-started in 38-s ML20062N1831982-08-12012 August 1982 Unique Rept 82-1:on 820706,diesel Fire Pump 1P-49 Declared Inoperable When Jacket Cooling Water Boiled Out During Surveillance Test.Caused by Abnormally High Operating Temp, Due to Malfunctioning Hx.Hx Cleaned & Repaired ML20062E5061982-08-0202 August 1982 Ro:On 820720,reactor Recirculation Jet Pumps Appeared Not to Meet Tech Spec Flow Balance Requirements.Event Determined Not Reportable,Since Event Constitutes Erroneous Test Criteria,Not Equipment Failure ML20055C0211982-07-29029 July 1982 Ro:On 820729,during Normal Operation Surveillance Testing, Differential Pressure Switches PDS-4304 & 4305 Tripped Out of Spec High at 0.65 & 0.7 Psid.Pressure Switches Recalibr & Functionally Tested ML20058J1071982-07-20020 July 1982 Ro:Recirculation Pump & Jet Pump Flow Instrumentation Indicated Flow Imbalance Between Two Recirculation Loops. Sixteen Jet Pumps Declared Inoperable.Orderly Shutdown Initiated to Cold Shutdown Conditions ML20058E6631982-07-14014 July 1982 Ro:Excessive Smearable & Fixed Contamination Levels Discovered Between Hittman Shipping Cask 600-2 & Trailer 72484 During Routine Survey.Supervisors Notified. Contamination Level Brought to Acceptable Limit ML20053E8911982-06-0303 June 1982 Ro:During Normal Operation,Msiv Position Indicating Switch, ZS4415,failed to Indicate Closure of CV4415 to Reactor Protection Sys.Caused by Broken Cap Screws Holding Speed Control Valve Manifold Assembly to Hydraulic Cylinder ML20069B0921981-12-11011 December 1981 Telecopy Message of Ro:On 811208 24-volt Dc Sys Trouble Alarm Received in Control Room.Output of Negative 24-volt Dc Charger 1D62 Was 21-volt Dc.No Definitive Cause Found. Event re-evaluated as 14-day RO on 811211 1998-07-14
[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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Iowa Electric Light and Ibwer Company August 3, 1983 DAEC 634 Mr. James G. Keppler Regional Administrator '
Region III U. S. Nuclear Regulatory Commission. '
799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Duane Arnold Energy Center Op. License No. DPR-49 Docket No. 50-331 Prompt Notification of a Reportable Occurrence File: A-118a .
Dear Mr. Keppler:
This ' letter telecopied to your office, provid.es written confirmation of a prompt notification pursuant to DAEC Technical Spacifications, Appendix A, Section 6.11.2.a.7. ~
On the morning of 8/3/83,'at approximately 0317 while performing. periodic surveillance testing on the RCIC System, discharge pressur,e instrument-PI 2506 displayed erroneous indications. Although this instrument.provides no automatic control functio _n, its failure prevents confirming RCIC discharge ~ pressure and flow as required in our surveillance procedure. The RCIC System, therefore,,
was declared inoperable. In accordance with DAEC technical spacifications,
~
Appendix A, surveillance testing of the HPCI and other. systems commenced.
At approximately 0417 hours0.00483 days <br />0.116 hours <br />6.894841e-4 weeks <br />1.586685e-4 months <br />, HPCI turbine speed indication failed downscale.
Although this instrument also performs no automatic' control function, HPCI was declared inoperable. _
Pursuant to technical specification 6.11.2.a and 10 CFR 50.72, notifications were made to the NRC and an unus'eal event declared: 'An orderly shutdown was ,
initiated in accordance with Technical Specification 3.5.D.3.
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Very truly yours, 8308220137 830803 PDR ADOCK 05000331 S
Daniel L. Mineck PDR Plant Superintendent - Nuclear Duane Arnold Energy Cer.ter -
DLM/WJM/pf .
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