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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARML20085A1141995-06-0808 June 1995 Ro:On 950525,ground Water Entered Containment at Rate of Approx One Gpm Until Approx 1300 Hs When Temporary Plug Was Installed Stopping in-leakage NRC-89-0042, Ro:On 890316,water Containing Radionuclide Concentrations in Excess of 10CFR20 Limits,Collected in Containment Vessel Sump.Water Originated from Condensation on Inside of Containment Vessel.Water Will Be Properly Disposed of1989-05-16016 May 1989 Ro:On 890316,water Containing Radionuclide Concentrations in Excess of 10CFR20 Limits,Collected in Containment Vessel Sump.Water Originated from Condensation on Inside of Containment Vessel.Water Will Be Properly Disposed of ML20151C6011988-04-0505 April 1988 Ro:On 880303,during First Quarterly Insp of 1988,water Noted to Have Collected in Containment Vessel Sump.Radioisotopic Analysis of Water Revealed That Contamination Exceeded 10CFR20 Limits for Unrestricted Release ML20236N4111987-11-0606 November 1987 Ro:On 870915,during Third Quarterly Insp of 1987,collection of Water in Containment Vessel Sump Noted.Caused by Condensation from Inside Containment Vessel.Periodic Monitoring,Removal & Disposal of Water Planned ML20207Q5591986-12-22022 December 1986 Ro:During Internal Review of Records for First Quarter 1986, Discovered Failure to Provide Written 15-day Notification of 860207 Contaminated Water in Containment Vessel Sump.Caused by Oversight ML20207Q5571986-12-0202 December 1986 Ro:On 861107,during Fourth Quarterly Insp,Radioactive Water Discovered Collecting in Containment Vessel Sump.Caused by Condensation.Water Will Be Monitored,Removed & Disposed of as Necessary.Results of Analysis Encl ML20079N5241983-12-30030 December 1983 Ro:On 831222,insp of Containment Vessel Sump Found 3.7 Cm of Water Below Elevation 765 ft-8 Inches.Caused by Condensation on Inside Walls of Containment Vessel Above Elevation 812 Ft.Sump Pumped Successfully ML20071D2351983-02-10010 February 1983 Ro:On 830118,4.5 Cm Water Found in Containment Vessel Sump, Below Elevation 765 ft,8 Inches Concentrations of Cs-134, Cs-137 & Sr-90 Confirmed.Pressure of Water Caused by Condensation on Inside Water.No Release to Environ ML20084N8061971-12-0909 December 1971 Ro:On 711129,while Operating Personnel Were Performing Primary Coolant Boron Dilution,Accidental Release of Radioactive Gases Occurred.Gases Released to Environ Via Plant Stack.No Overexposures Occurred ML20084N9571970-08-31031 August 1970 Ro:On 700826,accidental Release of Radioactive Gases Occurred During Switching of Gas Compressors to Locate & Isolate Minute Leak in Rwdf Sys.Cause Not Stated.Event Will Be Reviewed for Appropriate Corrective Action ML20084N9691970-05-18018 May 1970 Ro:On 700514,while Venting Gases from Primary Coolant Sys to Gas Compressor Sys,Accidental Release of Radioactive Gases Occurred.Caused by Rupture of Diaphragm in Gas Compressor Vacuum Regulating Valve ML20085H4851969-07-25025 July 1969 Ro:On 690725,upon Completion of Training Startup & Manually Tripping Reactor,Control Rod 6 Hung Up 36.6 Inches.Rod Removed Manually & Scrammed Into Fully Inserted Position ML20084P0041968-12-10010 December 1968 Ro:On 681126,while Transferring Water from Storage Well to Refueling Water Storage Tank,Approx 40 Gallons of Water Spilled on Floor of Safety Injection Sys Pump House.Caused by Personnel Error.Area Decontaminated by Washing ML20084P0111968-11-27027 November 1968 Ro:On 681004,following Completion of Operator Training, Erratic Instrument Response Observed on Steam Generator wide- & narrow-range Level Recorders & Pirmary Coolant Flow Recorder.Probably Caused by Instrumentation Problems ML20084P0221968-02-23023 February 1968 Ro:On 680122,control Rod 1 Did Not Drop to Normal Zero Position When Reactor Shut Down by Manual Scram of Control Rods.Probably Caused by Foreign Matl Lodged in Control Rod Drive Mechanism Dashpot ML20085D3621963-10-0909 October 1963 Ro:On 630809-19,three Unsuccessful Attempts Made to Pump Gas Into Gas Decay Tank 3.Caused by Small Hole Through Which Gas Was Escaping.Failure of Piping Caused by Impact of Tool or Falling Object 1995-06-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20209C0051998-12-31031 December 1998 1998 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20236N9161998-04-30030 April 1998 Rev 2 to Wmg 9801-7025, Saxton Reactor Pressure Vessel & Internals Final Characterization ML20217A9821998-04-20020 April 1998 Safety Evaluation Supporting Amend 15 to License DPR-4 ML20236N9101998-03-31031 March 1998 Rev 1 to Wmg 9803-7025, Saxton SG & Pressurizer Characterization. W/Supporting Documentation from Reactor Vessel Package ML20202B2541998-02-0202 February 1998 Rev 1 to Saxton Nuclear Experimental Corp Facility Decommissioning QA Plan ML20248D7181997-12-31031 December 1997 1997 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20210Q2321997-08-31031 August 1997 Rev 1 to Updated SAR for Decommissioning SNEC Facility ML20141C6661996-12-31031 December 1996 1996 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20134L8231996-10-28028 October 1996 Rev 0 to Saxton Nuclear Experimental Corp Facility Decommissioning Quality Assurance Plan ML20149K8121996-02-29029 February 1996 Rev 0 of SNEC Facility Decommissioning Plan ML20112C8451995-12-31031 December 1995 1995 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20116A1101995-12-12012 December 1995 Facility Reactor Vessel,Internals,Ex-Vessel Lead, Structural Steel & Reactor Compartment Concrete Shield Wall Radionuclide Inventory ML20087J7781995-06-27027 June 1995 Human Performance Enhancement Sys Rept Inadvertent Penetration of Saxton Containment Vessel Liner During Site Characterization Activities ML20085A1141995-06-0808 June 1995 Ro:On 950525,ground Water Entered Containment at Rate of Approx One Gpm Until Approx 1300 Hs When Temporary Plug Was Installed Stopping in-leakage ML20115K0821995-05-11011 May 1995 1994 Saxton Soil Remediation Project Rept ML20086B8561994-12-31031 December 1994 Experimental Corp 1994 Annual Rept for Saxton Nuclear Experimental Facility for 940101-1231 ML20070A3501993-12-31031 December 1993 SNEC 1993 Annual Rept Jan-Dec 1993 ML20056G8241993-08-31031 August 1993 Penelec/Gpu Internal Affairs Dept Williamsburg Incident Investigation 89-WM-2 ML20045D7161992-12-31031 December 1992 1992 Annual Rept for Saxton Nuclear Experimental Corp. W/ 930622 Ltr ML20101R2641992-03-31031 March 1992 Redacted Version of Penelec/Gpu Internal Affairs Dept Rept Williamsburg Incident Investigation 89-WM-2 ML20101L3341991-12-31031 December 1991 Experimental Corp 1991 Annual Rept. W/ ML20085C5901991-10-0404 October 1991 Rev 1 to Safeguards Rept for Saxton Core III ML20091D7351990-12-31031 December 1990 Facility 1990 Annual Rept ML20056A0181990-07-26026 July 1990 Trust Agreements ML20056A0091990-07-26026 July 1990 TMI-1 Trust Agreements ML20056A0021990-07-26026 July 1990 Trust Agreement Jcp&L Qualified Trust ML20043D7261989-12-31031 December 1989 Experimental Corp 1989 Annual Rept. W/ 900531 Ltr NRC-89-0042, Ro:On 890316,water Containing Radionuclide Concentrations in Excess of 10CFR20 Limits,Collected in Containment Vessel Sump.Water Originated from Condensation on Inside of Containment Vessel.Water Will Be Properly Disposed of1989-05-16016 May 1989 Ro:On 890316,water Containing Radionuclide Concentrations in Excess of 10CFR20 Limits,Collected in Containment Vessel Sump.Water Originated from Condensation on Inside of Containment Vessel.Water Will Be Properly Disposed of ML20247Q6891989-01-16016 January 1989 Rept on Drilling & Radiometric Analysis of Samples Collected at Sites of Spent Resin & Liquid Waste Tanks, Saxton Nuclear Facility,Saxton,Pa ML20247B2821988-12-31031 December 1988 SNEC 1988 Annual Rept ML20247Q6731988-12-20020 December 1988 Geologic,Chemical,Radiometric & Geotechnical Studies of Samples from Eleven Drill Holes in Surficial Matls,Saxton Nuclear Facility,Saxton,Pa. W/Seven Oversize Encls ML20151C6011988-04-0505 April 1988 Ro:On 880303,during First Quarterly Insp of 1988,water Noted to Have Collected in Containment Vessel Sump.Radioisotopic Analysis of Water Revealed That Contamination Exceeded 10CFR20 Limits for Unrestricted Release ML20236N4111987-11-0606 November 1987 Ro:On 870915,during Third Quarterly Insp of 1987,collection of Water in Containment Vessel Sump Noted.Caused by Condensation from Inside Containment Vessel.Periodic Monitoring,Removal & Disposal of Water Planned ML20206G0211986-12-31031 December 1986 Experimental Corp 1986 Annual Rept. W/ ML20207Q5591986-12-22022 December 1986 Ro:During Internal Review of Records for First Quarter 1986, Discovered Failure to Provide Written 15-day Notification of 860207 Contaminated Water in Containment Vessel Sump.Caused by Oversight ML20207Q5571986-12-0202 December 1986 Ro:On 861107,during Fourth Quarterly Insp,Radioactive Water Discovered Collecting in Containment Vessel Sump.Caused by Condensation.Water Will Be Monitored,Removed & Disposed of as Necessary.Results of Analysis Encl ML20214J2871985-12-31031 December 1985 Corrected Tables 1,2,3,5 & 6 to Saxton Nuclear Experimental Corp,1985 Annual Rept ML20141N5621985-12-31031 December 1985 Experimental Corp,1985 Annual Rept ML20099H6171984-12-31031 December 1984 Experimental Corp 1984 Annual Rept ML20086P2521983-12-31031 December 1983 Annual Rept,1983,Saxton Nuclear Experimental Corp ML20079N5241983-12-30030 December 1983 Ro:On 831222,insp of Containment Vessel Sump Found 3.7 Cm of Water Below Elevation 765 ft-8 Inches.Caused by Condensation on Inside Walls of Containment Vessel Above Elevation 812 Ft.Sump Pumped Successfully ML20073B5041983-04-0606 April 1983 Annual Rept for 1982 ML20071D2351983-02-10010 February 1983 Ro:On 830118,4.5 Cm Water Found in Containment Vessel Sump, Below Elevation 765 ft,8 Inches Concentrations of Cs-134, Cs-137 & Sr-90 Confirmed.Pressure of Water Caused by Condensation on Inside Water.No Release to Environ ML20052D8161982-04-27027 April 1982 Ro:On 820319,during Quarterly Facility insp,3.5 Inches of Water Found in Containment Vessel Sump.Analysis of Sump Water Confirmed Concentrations of Cs-134,Cs-137 & Sr-90 Exceeded Limits of 10CFR20 ML20041B8701982-02-16016 February 1982 Experimental Corp Annual Rept for Jan-Dec 1981. ML19337B6021980-09-25025 September 1980 Annual Rept for 1979. Describes Status of Decommissioning Facility ML19263C9051979-02-28028 February 1979 Annual Operating Rept 1978. ML20078A2881972-04-30030 April 1972 Analysis of Effects of Flooding on Saxton Containment Vessel ML20084N8061971-12-0909 December 1971 Ro:On 711129,while Operating Personnel Were Performing Primary Coolant Boron Dilution,Accidental Release of Radioactive Gases Occurred.Gases Released to Environ Via Plant Stack.No Overexposures Occurred ML20084N9571970-08-31031 August 1970 Ro:On 700826,accidental Release of Radioactive Gases Occurred During Switching of Gas Compressors to Locate & Isolate Minute Leak in Rwdf Sys.Cause Not Stated.Event Will Be Reviewed for Appropriate Corrective Action 1998-04-30
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February 23, 1968 1
lj Docket No. 59=tr16 8 8 N b
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11r. Donald J. Skovholt Assistant, Director for Reactor Operations Divinicu of Reactar Licensing U.S. Atomic Energy Commission Washington, D.C. 20545
Dear IIr. Skovholt:
) During January 1968, the Saxton reactor was being utilized for reactor
- operator start-up training with the primary coolant systera at operating pressure a
and temperature and nomal flow. On January 22, following completion of the day'a training, the reactor was shutdown by manual scram of the control rods.
( Control rod No.1, however, did rot drop to its nomal zero position, stopping
, at '!.98 inenca above zero. A subsequent rod exercise program resolved the difficulty with this rod.
] 'Ine difficulty experienced with No.1 control rod was reported to the Region I Compliance Office and to Division of Reactor Licensing by telephone on January 29, imd 13 herewith reported in writing in compliance with paragraph
{ 3 E(1) of the Saxton Operating License DPR-4.
With the reactor shutdown, an exercise program for No. 1 control rod was initiated to resolve or. further define the problem. Fifteen drops were made 4
from 40 inches; however, on the 16th drop the rod stopped at 3 22 inches above p itu zero position. Following this,14 drops were made from 40 inches, and 34 4 drops were made fron 10 inches without difficulty. On the 35th drop from 10 inchen, the rod stopped at 2.97 inches above its zero position. Rod exercise was continued for an additional 50 drops without further difficulty.
I Rod withdrawal rates and drop times were measured and compared with previous data. All were nomal.
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i The difficulty experienced with this rod was reviewed by the Saxton
- On-Site Safety Carnittee and by the reactor manufacturer. It was concluded that probably a small piece of foreign material was lodged in the control rod drive mechanium dashpot and that it was subsequent.ly removed by the self-flushing action of the dashpot during the rod drops.
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Sincerely, F - .j f
General Manager y ec: G. F. Trowbridge, Esquire s
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