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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARCY-99-047, Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use1999-03-23023 March 1999 Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use CY-98-136, Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line1998-08-12012 August 1998 Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line CY-98-068, Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms1998-04-15015 April 1998 Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms CY-98-045, Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing1998-04-13013 April 1998 Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing CY-98-046, Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal1998-03-12012 March 1998 Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal CY-97-082, Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys1997-08-14014 August 1997 Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys B16268, Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor1997-02-19019 February 1997 Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor B15833, Ro:On 960904,loss of Reactor Coolant Sys Inventory Occurred. Caused by Leakage Past RH-V-23A.Issued Stop Work Order & Developed Plan to Review All Outage Work Orders Against Shutdown Risk Mgt Program Key Safety Functions1996-09-0505 September 1996 Ro:On 960904,loss of Reactor Coolant Sys Inventory Occurred. Caused by Leakage Past RH-V-23A.Issued Stop Work Order & Developed Plan to Review All Outage Work Orders Against Shutdown Risk Mgt Program Key Safety Functions ML20058G2431993-12-0202 December 1993 Special Rept:On 931116,routine Surveillance Testing of Wide Range Noble Gas Stack Monitor RMS-14B Completed.Caused by Damaged Calibr Source.New Calibr Source Being Procured & Low Range Channel Detector Will Be Recalibrated to New Source ML20058Q1101990-08-10010 August 1990 Special Rept:On 900727,accident Monitoring Instrumentation Found Inoperable for Core Exit Thermocouple.Troubleshooting Initiated.Util Working W/Vendor to Procure Fully Qualified Replacement Cable ML20248A5741989-09-26026 September 1989 Special Rept:On 890917,quarterly Beta Dose Limit of 10 Mrad for Noble Gases Exceeded.Caused by Degasification of Reactor Coolant Coincident W/Higher than Normal Radioactive Gas Concentration.Degasification Process Completed ML20244A6601989-04-0606 April 1989 Special Rept:On 890309,diesel Fire Pump Declared Inoperable as Result of Failure to Automatically Shut.Caused by Failure of Solenoid Valve Controlling Inlet Flow to Hydraulic Governor Device.Redundant Fire Water Supply Provided ML20153D4911988-05-0202 May 1988 Ro:On 871219 & 880314,spills of Lubricating Oil Occurred. Caused by Equipment Failure in Travelling Water Screen in Cooling Water Intake Structure & Faulty Fitting on Auxiliary Feed Pump.Screen & Fitting on Pump Repaired ML20147C5751988-01-12012 January 1988 Ro:On 871219,1 Quart of Lubricating Oil Leaked from Travelling Water Screen in Cooling Water Intake Structure & Entered Connecticut River.Caused by Equipment Failure.Cause of Spill Corrected ML20141C9551986-03-0101 March 1986 Special Rept:During Fourth Quarter 1985,river Water Sample Determined to Exceed Control Station by Factor of Ten. Caused by Increased Amount of Primary Water Processed.No Corrective Actions Required Due to Insignificant Levels ML20126F1211975-04-0101 April 1975 RO 50-213/75-1:on 750326,packing Gland Leak Rate Exceeded Tech Specs & Valve Steam Leak Offline Pressurized Enough to Lift Sys Valve,Relieving Pressure to Containment Sump.Caused by Inner Set of Packing Failure on Letdown Isolation Valve 1999-03-23
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 CY-99-047, Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use1999-03-23023 March 1999 Ro:On 981217,identified Unsuccessful Dewatering of Cnsi HIC, Model PL8-120R,containing Resins.Caused by Apparent Failure of Dewatering Tree.Other HICs Have Been Procured,Recertified & Returned to Plant for Use ML20206F1971998-12-31031 December 1998 Annual Rept for 1998 for Cyap. with CY-99-027, Annual Rept for 10CFR50.59, for Jan-Dec 1998.With1998-12-31031 December 1998 Annual Rept for 10CFR50.59, for Jan-Dec 1998.With ML20198G9101998-12-22022 December 1998 Proposed Rev 2 of Cyap QAP for Haddam Neck Plant. Marked Up Rev 1 Included ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co CY-98-136, Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line1998-08-12012 August 1998 Ro:On 980727,flow Blockage Occurred & Caused Pressure in Sys to Increase,Resulting in Relief Valve Lifting & Pipe Vibration,Which Caused Leaks to Develop.Caused by Nearly Closed post-filter Inlet Valve.Repaired 2 Leaks in Line ML20237B7461998-07-22022 July 1998 1998 Defueled Emergency Plan Exercise Scenario Manual, Conducted on 980722 ML20202D1621998-06-30030 June 1998 Safety Evaluation Supporting Amend 193 to License DPR-61 CY-98-068, Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms1998-04-15015 April 1998 Follow-up to Verbal Notification on 980413 of Film on Discharge Canal.Investigation Continuing.Samples Collected for Petroleum Analyses & Biological Characterization at Intake Structure & Discharge Canal.Replaced Sorbent Booms CY-98-045, Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing1998-04-13013 April 1998 Ro:On 980212,0219,0225 & 0312,separate Sheens of Approx One Cup of oil-like Substance Was Observed at Discharge Canal. Cause Has Not Been Clearly Identified.Called in Vendor Spill to Install Sorbent Booms to Absorb Sheen.W/One Drawing ML20217F0611998-03-31031 March 1998 Historical Review Team Rept ML20217A0001998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Haddam Neck Plant ML20217K2101998-03-27027 March 1998 Safety Evaluation Supporting Amend 192 to License DPR-61 CY-98-046, Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal1998-03-12012 March 1998 Follow-up to 980311 Verbal Notification of Film on Discharge Canal.Cause Not Yet Determined.Film Is Contained & Will Be Absorbed by Containment & Sorbent Booms That Were in Place in Discharge Canal ML20216D6531998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Haddam Neck Plant ML20217D7381998-02-28028 February 1998 Revised MOR for Feb 1998 Haddam Neck Plant CY-98-012, Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant1998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Connecticut Yankee Haddam Neck Plant CY-98-010, Annual Rept for 10CFR50.59,Jan-Dec,19971997-12-31031 December 1997 Annual Rept for 10CFR50.59,Jan-Dec,1997 ML20198N6681997-12-31031 December 1997 Monthly Operating Rept for Dec 1997 for Haddam Neck Plant ML20217P4861997-12-31031 December 1997 1997 Annual Financial Rept, for Cyap ML20199L5891997-12-24024 December 1997 Independent Analysis & Evaluation of AM-241 & Transuranics & Subsequent Dose to Two Male Workers at Connecticut Yankee Atomic Power Plant ML20203K4271997-11-30030 November 1997 Monthly Operating Rept for Nov 1997 for Haddam Neck Plant ML20199B1141997-10-31031 October 1997 Monthly Operating Rept for Oct 1997 for Haddam Neck Plant ML20198M8101997-10-14014 October 1997 SER Accepting Proposed Revs to Util Quality Assurance Program at Facility ML20198J8811997-09-30030 September 1997 Monthly Operating Rept for Sept 1997 for Haddam Neck Plant ML20210P8721997-08-31031 August 1997 Post Decommissioning Activities Rept, for Aug 1997 ML20217Q3171997-08-31031 August 1997 Addl Changes to Proposed Rev 1 to QA Program ML20210U9301997-08-31031 August 1997 Monthly Operating Rept for Aug 1997 for Haddam Neck Plant CY-97-082, Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys1997-08-14014 August 1997 Special Rept:On 970708,routine Surveillance Testing of Seismic Monitoring Sys Instrumentation Revealed,Data Was Not Being Reproduced by Portion of Playback Sys.Station Presently Pursuing Replacement of Seismic Monitoring Sys ML20210L0521997-07-31031 July 1997 Monthly Operating Rept for July 1997 for HNP ML20149E4451997-06-30030 June 1997 Monthly Operating Rept for June 1997 for Haddam Neck Plant ML20141A0041997-05-31031 May 1997 Independent Assessment of Radiological Controls Program at Cyap Haddam Neck Plant Final Rept May 1997 ML20140H5241997-05-31031 May 1997 Monthly Operating Rept for May 1997 for Haddam Neck Plant ML20141K4201997-05-22022 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-61 ML20141D4141997-04-30030 April 1997 Monthly Operating Rept for Apr 1997 for Connecticut Yankee Haddam Neck ML20138G5901997-04-25025 April 1997 Proposed Rev 1 to Cyap QA Program for Haddam Neck Plant ML20137W8051997-03-31031 March 1997 Monthly Operating Rept for Mar 1997 for Haddam Neck Plant ML20137H3031997-03-31031 March 1997 Rev 2 to Nuclear Training Loit/Lout Audit Reviews ML20137C6281997-03-14014 March 1997 Redacted Version of Rev 1 to Nuclear Training Loit/Lout Audit Reviews ML20137A0801997-02-28028 February 1997 Monthly Operating Rept for Feb 1997 for Haddam Neck Plant ML20135C5101997-02-26026 February 1997 1996 Refuel Outage ISI Summary Rept for CT Yankee Atomic Power Co B16268, Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor1997-02-19019 February 1997 Special Rept:On 970205,declared Main Stack-Wide Range Noble Gas Monitor Inoperable.Caused by Inadequate Calibr Methods. Will Revise Calibr Procedure to Technique to Demonstrate Accuracy & Linearity Over Intended Range of Monitor ML20135E3221997-02-13013 February 1997 Independent Review Team Rept 1996 MP -1 Lout NRC Exam Failures ML20134L2751997-02-0303 February 1997 Draft Rev to GPRI-30, Spent Fuel Storage Facility Licensing Basis/Design Basis ML20138K5721997-01-31031 January 1997 Monthly Operating Rept for Jan 1997 for Haddam Neck Plant.W/ ML20134L2791997-01-10010 January 1997 Rev 0 to QA Program Grpi ML20134L2911997-01-0808 January 1997 Rev 0 to UFSAR Rev Grpi ML20134L2721996-12-31031 December 1996 Commitment Mgt Grpi 1999-04-28
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,w CONNECTICUT YANKEE ATOMIC POWER COMP ANY B E R L I N. CONNECTICUT P.O. BOX 270 HARTFORD, CONNECTICUT 06141-0270 TELEPHONE '
203-665-5000 Dr. T. E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Reference:
Facility Operating License No. DPR-61 Docket No. 50-213 ETS-NR/50-213/86-01
Dear Dr. Murley:
During the fourth quarter of 1985 a river water sample was obtained that was determined to require a written report because of the level of radioactivity observed. The result of the analysis on this sample was received on February 19, 1986 and therefore was during the period for which new Technical Specification requirements were in place. (The Radiological Effluent Technical Specifications were implemented January 1, 1986). Under these new Specifications no report is required. However, because the sampling occurred during the fourth quarter of 1985, pursuant to the now outdated Haddam Neck Environmental Technical Specification Section 3.2, the Haddam Neck Plant hereby forwards the following report regarding the measurement of anomalous radioactivity in river water.
Very truly yours, M"
Richard H. Graves ;
Plant Superintendent j RilG/RC/kav Enclosure cc: Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 j
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Facility: Haddam Neck Nuclear Facility Report Number: ETS/NR/50-213/86-01 Report Date: March 1, 1986 Occurrence Date: Fourth Quarter, 1985 DESCRIPTION OF OCCURRENCE:
The following level of tritium (H-3) activity was observed in the quarterly composite of river water near the discharge area. This value exceeded the control station (Middletown) by greater than a factor of ten.
Analysis Results Sample Dates Report Date (pCi/1)
Discharge Area Continuous 9/30-12/30 2/19 870170 Middletown Weekly grabs 10/1-11/5 -
74166 (control)
PLANT OPERATING CONDITIONS PRIOR TO OCCURRENCE:
The plant was operating at about 100% power except for a coast down during December in advance of a January 4, 1986 refueling outage. During the quarter, primary systems were being processed in preparation for the refueling outage.
CAUSE OF OCCURRENCE:
Due to the increased amount of primary water which must be processed in preparation for a refueling outage, the amcunt of radioactivity released in liquid discharges is typically higher during the few months preceding plant shutdown. The levels at the control location were lower than normal due to the higher than routine sensitivity of the analysis.
These factors resulted in river water tritium levels approximately 20% greater than an overly conservative reporting limit (see Dose Consequences).
DOSE CONSEQUENCES: 1
% l A dose calculation using Regulatory Guide 1.109 methodology was performed. :
The calculation assumed an individiual could have consumed fish, resident in l river water having the tritium concentration as measured. The whole body dose would be 0.0005 mrem. There is no drinking sater pathway. A more conservative calculation is to again use the Regulatory Guide 1.109 methods and the measured plant discharges for this quarter. This results in the calculation of 0.0035 mrem for the 4th quarter. These calculations are conservative in that the fish do not reside at this location of maximum l activity 100% of the time. The calculated dose of 0.0035 mrem is an extremely small fraction (approximately 0.0001) of the natural background radiation (30 l
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mrem) to which this individual is normally exposed over this period of time (three months). Thus the dose consequence of this event is insignificant.
4 Since these samples were collected during the 4th quarter of 1985, the reporting requirements effective at that time were used. As of January 1986, 4
these over conservative reporting requirements-have been changed with the implementation of the radiological effluent technical specifications (RETS).
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The revised safety technical-specifications which incorporate the RETS, would not require any such action until tritium levels' reach 20,000 pCi/1.
Therefore, no other corrective actions are required due to the insignificance of the measured levels.
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