|
---|
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
[Table view] |
Text
_
,u Iowa Electric l.ight and ther Company August 12, 1982 DAEC 543 l
l Mr. James G. Keppler Regional Administrator Region III U. S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 1
Re: Duane Arnold Energy Center i
Subject:
Unique Report 82-1 File: A-ll8, NRC-1
Dear Mr. Keppler:
This report is submitted in accordance with the requirements of Appendix A to Operating License DPR-49, Specification 6.11.3.
Problem On July 6,1982, diesel fire pump IP-49 was declared inoperable when the jacket cooling water was lost following 30 minutes of pump operation for a weekly surveillance test. The closed-circuit jacket cooling water boiled out through a relief valve less.than 2 seconds after the diesel fire pump was secured, apparently from abnormally high engine operating temperature.
Electric fire pump 1P-48 was demonstrated operable inanediately. and daily thereafter in accordance with Technical. Specification 4.13.B.2, with the .
exception that IP-48 was inadvertently not demonstrated operable for three l days (July 15-17,1982) while diesel fire pump 1P-49 was inoperable. Diesel fire pump 1P-49 was made operable after 13 days, on July 19, 1982. This 13-day period exceeded the 7 days.specified by Technical Specification 3.13.B.2..
The plant was in cold shutdown during the time that diesel fire pump 1P-49 was inoperable.
Cause The abnormally high diesel. engine operating temperature was caused by a malfunctioning jacket cooling water heat: exchanger. The 13-day diesel fire pump downtime included troubleshooting the overheating problem, repairs to
.the heat exchanger, and the performance of annual maintenance items. The troubleshooting required the use of two test rigs whose fabrication required several days.
~
8208230037 820812 )
gDR ADOCK 05000 j h k' Ikww Arwid Duergv Center in Ikss 351
- Cedar Itapids, Iona 52406
'g-}g M
/
Mr. James G. Keppler August 12, 1982 Page 2 Investigation into the root cause of the f ailure to perform serveillance on the three days as specified above is continuing.
Corrective Action The diesel fire pump jacket cooling water heat exchanger was cleaned and one leaking tube was plugged. A new thermostat was installed and all annual maintenance items were checked. Parts replaced include the oil, oil filter, fuel filter, coolant, coolant filter, and coolant hoses. After the maintenance and repairs were completed, diesel fire pump 1P-49 was functionally tested satisfactorily.
Because the diesel engine still runs at the high end of the acceptable operating temperature range, a design review of the adequacy of cooling water flow to the shell side of the jacket cooling water heat exchanger will be performed.
Appropriate personnel have been reinstructed on the procedural controls that assure that surveillance requirements are met for inoperable equipment.
Additional corrective action as determined by further investigation will be implemented as appropriate and an update report will be submitted by August 31, 1982.
This report has been reviewed.by the DAEC Operations Committee.
Very truly yours,
'7 Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/DMV/pl Docket No. 50-0331 cc: Resident NRC Inspector - DAEC 8
I L. A