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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20210J2921999-07-29029 July 1999 Special Rept:On 990406,OG TS & Associated Charcoal Absorbers Were Removed from Svc.Caused by Scheduled Maint on Hpci. Evaluation of Offsite Effluent Release Dose Effects Was Performed to Ensure Plant Remained in Compliance ML20202G2821997-12-0404 December 1997 Special Rept:On 971014,discovered Hydrogen Burn in Off Gas Sys Was Received.Caused by Valve Malfunction.Maint Was Performed on Aog Sys Components to Assure Reliability of Components During Restart Process ML20211H6861997-09-29029 September 1997 Special Rept:On 970713,high Influx of Water Into Z Sump Resulted in SGT Sys Being Declared Inoperable.Caused by Effects of Operation W/Aog Isolated.District Developed & Implementing Design Change to Prevent Excessive Water ML20137C2421997-03-17017 March 1997 Special Rept:On 970301,electric-driven Fire Pump Made Inoperable Due to Overheating of Pump During Low Flow operation.Electric-driven Fire Pump FP-P-E Restored ML20134N1641996-11-20020 November 1996 Special Rept:On 961119,Fire Suppression Water (Fsw) Sys Declared Inoperable.Caused by Fire Pumps Being Placed in pull-to-lock Position to Accommodate Planned Maint on Fsw Sys.Pumps Returned to Service Upon Completion of Maint ML20101J5591996-03-27027 March 1996 Special Rept:On 960326,electric-driven & diesel-driven Fire Pumps Were Placed in pull-to-lock Position to Prevent Inadvertent Pump Starts During Restoration & Acceptance Testing.Fire Water Pumps Returned to Service ML20101J1561996-03-26026 March 1996 Special Rept:On 960325,electric-driven & diesel-driven Fire Pumps Placed in pull-to-lock Position to Prevent Inadvertent Pump Start During testing.Electric-driven & diesel-driven Fire Water Pumps Returned to Services Following Maint ML20095C1951995-12-0808 December 1995 Special Rept:On 951205,both electric-driven & diesel-driven Fire Pumps Placed in pull-to-lock Position to Accommodate Preventive Maint on Fire Water Jockey Pump.Caused by Erroneous Pump Starts.Returned Pumps to Svc ML20083N2641995-05-16016 May 1995 Special Rept:On 950515,loss of Switchyard 12.5 Kv Power Resulted in Temporary Inoperability of Fire Suppression Water Sys.Caused by Short Circuit Due to Failed Shield Wire. Pumps Restored to Normal Switch Configurations ML20082F4861995-03-31031 March 1995 Special Rept:On 950220,steam Jet Air Ejectors Placed Into Svc.At Same Time Augmented off-gas Treatment Sys in Svc & Charcoal Beds Bypassed Due to High Indicated Moisture in Air Stream.Moisture Indication Corrected ML20092E4431992-02-0808 February 1992 Ro:On 920207 250 Volt Battery Sys a Declared Inoperable Per TS 3.8.B.1.c Pending Cell 110 Replacement.Nuclear Safety & Engineered Safety Sys Operating Under B Sys Which Will Be Monitored Daily.Replacement Cell Being Prepared ML20237H0801987-08-0808 August 1987 Ro:On 870808,annunciator Received in Control Room Indicating That One Air Operated Vacuum Breaker Moved from Closed Position to Intermediate Position.Caused by Failed Gasket on Air Supply Filter.Repairs Completed ML20214M8521987-05-19019 May 1987 Ro:On 870518,reactor Scrammed Due to Reactor Conductivity Exceeding Tech Spec Limits.Caused by Tube Rupture within Main Condenser.Repairs Underway ML20210R3721986-09-22022 September 1986 Ro:On 860921,drywell Floor & Equipment Sump Integrator Registered 5.65 Gpm Leak Rate.Caused by Packing Leak on Recirculation Loop Discharge Valve a Discovered on 860922. Repairs Completed ML20211E6171986-06-0606 June 1986 Ro:On 860603,rail Shipment of Empty IF-300 Cask Containing Residual Contamination Received at Facility.Contamination Appeared Leaching Out from Cask External Surfaces.Reading Greater than Limits in 10CFR20.205 ML20210N4401986-04-21021 April 1986 Ro:On 860418,empty IF-300 Cask,Serial IF-301,received w/11 Smearable Contamination Readings Exceeding 22,000 Beta & Gamma dpm/100 cm(2) Allowed in 10CFR205,but Not Exceeding Regulatory Limits Per 10CFR71.87 & 49CFR173.443 ML20136E6091985-12-23023 December 1985 Ro:On 851223,unusual Event Declared When RHR Valve & Svc Water Booster Pump Inoperative.Caused by Poor Connection in Control Wiring of Valve Motor Starter.Insp of RHR Injection Valve Electrical Connections Underway ML20135B6021985-08-26026 August 1985 Ro:On 850824,meteorological Sys Trouble Alarm Received by Control Room on Board VBD-Q.Caused by Lost Control Program on Computer Controlling Meteorological Sys.Design Mod Initiated ML20132G9971985-07-19019 July 1985 Ro:On 850719,meteorological Sys Trouble Alarm Received by Control Room W/Reactor in Cold Shutdown.Caused by Lightning Strike on Meteorological Data Tower.Appropriate Notifications Initiated & Repairs Effected ML20113C3881985-03-27027 March 1985 Ro:On 850327,personnel Injured in Drywell.Caused by Fall from Ladder.Individual Transported to Hosp in Protective Clothing.No Contamination Noted.Patient Will Remain Hospitalized for 24 H ML20099C1941984-06-22022 June 1984 Ro:On 840614,due to Series of Extremely Heavy Rains in Areas Upstream of Plant,Flood Control Actions Initiated Per Emergency Procedure 5.1.3.Deescalation from Unusual Event Classification Ordered on 840621 ML20092D6921984-04-20020 April 1984 Ro:On 840419,standby Gas Treatment Trains Inoperable.Caused by Const Bulldozer Shearing Off Fire Hydrant,Causing Fire Protection Sys to Lose Pressure.Charcoal Adsorbers Replaced. Procedures Controlling Const Activities Implemented ML20084H5081984-01-0505 January 1984 Ro:During Environ Testing of Operability in Harsh Environ, Electrical Panelboard Switch Installed in safety-related Sys Failed.No Immediate Corrective Action Necessary 1999-07-29
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML20210R0381999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Cooper Nuclear Station ML20210J2921999-07-29029 July 1999 Special Rept:On 990406,OG TS & Associated Charcoal Absorbers Were Removed from Svc.Caused by Scheduled Maint on Hpci. Evaluation of Offsite Effluent Release Dose Effects Was Performed to Ensure Plant Remained in Compliance ML20209H8281999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209E1061999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Cns.With ML20196B3851999-06-17017 June 1999 Summary Rept of Facility Changes,Test & Experiments,Per 10CFR50.59 for Period 970901-990331.Summary of Commitment Changes Made During Same Time Period Also Encl ML20195K2851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Cooper Nuclear Station.With ML20206P0481999-05-12012 May 1999 Safety Evaluation Concluding That NPP Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at CNS & Adequately Addressed Actions Requested in GL 96-05 ML20206J0811999-05-0404 May 1999 Rev 14 to CNS QA Program for Operation ML20206P9751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station ML20205Q0891999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Cooper Nuclear Station.With ML20204G8951999-03-15015 March 1999 CNS Inservice Insp Summary Rept Fall 1998 Refueling Outage (RFO-18) ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204B3701999-03-11011 March 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Requests for Relief for RI-17,Rev 1 and RI-25,Rev 0.Request for Relief RI-13,Rev 2 Involving Snubber Testing & Is Being Evaluated in Separate Report ML20204C9751999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station ML20199E6751999-01-14014 January 1999 Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station ML20195B9191998-12-31031 December 1998 1998 NPPD Annual Rept. with ML20196J9641998-12-0707 December 1998 Safety Evaluation Accepting Licensee Third 10-yr Interval Inservice Insp Plan Request for Relief RI-27,rev 1 ML20198D2471998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Cooper Nuclear Station.With ML20196A2861998-11-23023 November 1998 SER Re Core Spray Piping Weld for Cooper Nuclear Station. Staff Concluded That Operation During Cycle 19 Acceptable with Indication re-examined During RFO 18 ML20196A5241998-11-23023 November 1998 Safety Evaluation Accepting Proposed Alternative to Use UT Techniques Qualified to Objectives of App Viil as Implemented by PDI Program in Performing RPV Shell Weld & Shell to Flange Weld Examinations ML20196A5061998-11-23023 November 1998 Safety Evaluation Re Flaw Indication Found in Main Steam Nozzle to Shell Weld NVE-BD-N3A at Cns.Plant Can Be Safely Operated for at Least One Fuel Cycle with Indication in as-is Condition ML20196C4241998-11-20020 November 1998 Rev 1 to Cooper Nuclear Station COLR Cycle 19 ML20195H1761998-11-17017 November 1998 SER Authorizing Proposed Alternative in Relief Requests RV-06,RV-07,RV-09,RV-11,RV-12 & RV-15 Pursuant to 10CFR50.55a(a)(3)(ii).RV-08 Granted Pursuant to 10CFR50.55a(f)(6)(i) & RV-13 Acceptable Under OM-10 ML20195F8601998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Cooper Nuclear Station.With ML20155D9961998-10-31031 October 1998 Rev 0 to GE-NE-B13-01980-24, Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station ML20154Q5661998-10-0505 October 1998 Rev 0 to CNS COLR Cycle 19 ML20154L5381998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Cooper Nuclear Station.With ML20151Z6141998-09-16016 September 1998 SER Accepting Util Responses to NRC Bulletin 95-002 for Cooper Nuclear Station ML20154F7931998-08-31031 August 1998 Rev 0 to J11-03354-10, Supplemental Reload Licensing Rept for CNS Reload 18,Cycle 19 ML20153B1101998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Cooper Nuclear Station ML20237E7771998-08-20020 August 1998 Revised COLR Cycle 18 for Cooper Nuclear Station ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C0591998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Cooper Nuclear Station ML20236R9131998-07-20020 July 1998 SER Accepting Rev 13 to Quality Assurance Program for Operation Policy Document for Plant ML20236P2971998-07-0707 July 1998 Rev 2 to NPPD CNS Strategy for Achieving Engineering Excellence ML20236R0931998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Cooper Nuclear Station ML20249A7701998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Cooper Nuclear Station ML20247G6131998-05-13013 May 1998 Part 21 Rept Re Defect Contained in Automatic Switch Co, Solenoid Valves,Purchased Under Purchase Order (Po) 970161. Caused by Presence of Brass Strands.Replaced Defective Valves ML20247G0951998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Cooper Nuclear Station ML20237B6861998-04-24024 April 1998 Vols I & II to CNS 1998 Biennial Emergency Exercise Scenario, Scheduled for 980609 ML20217A1531998-04-16016 April 1998 Closure to Interim Part 21 Rept Submitted to NRC on 970929. New Date Established for Completion of Level I & 2 Setpoint Project Committed to in .Final Approval of Setpoint Calculations Will Be Completed by 980531 ML20216G5331998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Cooper Nuclear Station 1999-09-30
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1 Mr. J. F. Gagliardo, Chief APR 2 S1986 Reactor Projects Branch jL' U. S. Nuclear Regulatory Commission J_'-
-- l Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011
Subject:
10CFR20.205.(b)(2) Notification
Dear Mr. Gagliardo:
This letter is a followup to the telephone notification made to Mr. R. Baer, USNRC Region IV Office, on April 18, 1986. As discussed with Mr. Baer, a rail shipment of one empty IF-300 c Serial Number IF-301, containing only residual contamination was rer by Nebraska Public Power District at 0930 April 18, 1986. All shipping e._ ria were met with the exception of eleven smearable contamination readings on the cask. These readings were greater than the 22,000 beta and gamma dpm/100 cm2 allowed in 10CFR20.205. It did not appear that this contamination resulted from leakage of the radioactive contents of the cask, but rather from contamination leaching out from the cask external surfaces.
As allowed in 10CFR71.87 and 49CFR173.443, other methods of contamination assessment were used and the results showed that in no case did the surface contamination on the external surfaces of the package exceed the regulatory limits as defined in 10CFR71.87 and 49CFR173.443.
If you have any questions regarding this letter, please contact me at the site.
Sincprely, p ._
G. (. Horn Division Manager of Nuclear Operations GRH:RJM:ya 860505003 PDR 21 S ADOCX 05000298 PDR cc: L. G. Kuncl g tCO J. M. Pilant e y) g
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