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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
[Table view] |
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. . . _ - - - - - - a g t. iou-y, SAX.ON NUCLEAR EXPERIMElJAL CORPORATION n,
GENERAL P U B LIC UTILITIES SYSTEM j
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P.dsnhear#2deedsman fag suten 63N937 r.3. nex 99, saxton, Pa.
october 9, 196)
Director Division of Liomuttng and Eagulation U.S. Ateenio Energy Cammaission vashington 25, D.C.
Deer Sirs i
The folluving report of an inaident kt baxton involving the unintentional release of a -11 quantity (less than 2 millieuries) of radiomative gas is formrded. Saxton does not believe that a report is requird by our license s#R-4 since no poemible unute condition satisted, nor did the release rwtuire reporting I
by AEC Regulation ID CDL 20J bowever, our AEC sempliance inepeeter stated that 1%
his opinion a report is required by our lieanse DPn-A paragrege 3 D (1) so we are l
I forwarding this report for your infomation.
hinoersly, W. 61. Iayman General Manager oos Manager, New Yoric '#eration Office LMARC 376 Hudson Street, New York 14, N.Y.
G. RLeewe, fAM Safety Committee J. O'Rielly G. F. Trowbridge .
S. R2rtnoff kNykON y
tu c m _jfu *10424 g,
Saxton Ihtalear %tal Oermerstism l Inciduit Remrt 9
Litt intentional Release _tr<m oss Decar Tank .11.3 Resorintion of grants During the period August 9,1%) through August 19,1%) three unsueeessful attempts were made to psap gas into the No. 3 Qas Decay Tank which is a part of the gas handling systen in the Radiactive kaste Disposal Fasility at the Saxtsu Reaster Plant. Pressure failed to build-up in the tank each time it ws placed in service.
Following %e first attempt, the rupture diso which protects the tank from crerpreocure was inspected and found to be intact and a osall leak at one of the tank instrunernt lines was located and repaired. The eeoand attempt to pump gas into t!.e tank occurred on August 17. Folicwing this attenpt, the npture disc was again renoved and tested arid a ==411 leak was discovered. A new rupture dine we installed arxi a thid attetapt to use Oas Decay Tank No. 3 was made on August 19. After coveral hours operation the tank was again taken out of service since no prwsure build-up was obearved.
h gas decay tanks and satch of their associated piping are located epproximately six feet below trutnd level ant adjasant to W Waste Lispoul Plant.
The remainder of the piping connooted to %ese tanks is located in the pipe tunnel ami Waste Disposal Plant. It was apparent Wt aneWr leak existed and hat a testing program wa necessary to inoate W leak. All leak tests wre contuoted with non-radiomative nitrogen gas. Testa were first conducted to determine if the leak was located in the exposed piping or through valves located in the esposed piping eennected to the tank. No leaks were located by those tuts so it was decided to dig a series of holes in the plant yard, first at those lomtions where be pipes eaanesting Gas Decay Tank No. 3 pass through the wil of We pipe tunnel. The procedure used was to excavate to the water table and loosen the ear % around the pipe balow. The tank wss them pressurised to approvinately 30 peig and the bottaa of the exoavation was observed for 24 appearanoe of gas bubbles in W water. The socoed such test located no ink approscinately 2 feet from W tumnal wall in a !" line whiek is provided to drain any liquid in the gas doeay tank to one of W 10,000 gallen underground storage tanks. The maali hole through which gas was escaping was located in an indsettation in tho top of the pipe. The indentation probably was caused by We impact of a tool or faliina object during plant eonstruction. The tank and associated piping entisfactorily passed strength and leak tests before plant operation began. It is believed that the failure was eausad hy a weakening of the pipe well es a roeuh, of W indentation.
Radiolerieal Durvaars At the time the leak was leested and also during previous exoavation procedures, radiation survers with a aide-window Q-M surver meter did not indiosto any radioaotivity above background either in W vicinity of the essavations or en maintenance personnel perfonsing the wed. After W Ink ms loonted, ground water samples were ecllected and analysed and it we detenmined that the grose beta-gamma activity was lose than the average background activity of the adjacent Raysteun Rranch of W Amiata River.
L l
In addities, the rooeNo of W aff-aits andiation sureg stations were studied for the period August 9 through August 19 during whiek attempts were made to pump plant eft-gases into Osa Deear Fank so. 3. This study imileated that W two, contirmously roeordad, eft-site, moving filter paper type, radiation monitertag snannels (RIC.4 and RIC-9) did not reced av ehange in the normal haakground ruiioactivity. The reseMs of a meteorological enreg station leested adjasent to the plant site whian sentinuously records wiad velasity and directies were alas studied and these records indleate hat the prevailing wimde during he paried were fron the soun-west, which is the direction from the leaking drain line to the radiation monitaring ehannel AIC 4 The neerds of armlyses of the fixed-fLiter paper type, air partlealate sunpler fran Livtronmental Radiation Survey Station No. I were alas studied. This station is located appmximately 600 feet east of the leoation of the leak. These recoNo indicate tnat a tilter paper which was in service during the period August 9 thrvugh August 19 oollected background radioactivity in an amount consistunt with the airbome activity being observed at this survaqr station during the enamner of 1%).
Based on the foregoing ebaarvations, it was oancluded that particulate radioactivity was not released. However, it was recognised that thc. fission gases Krd) and Isl33 may have beau released and an analysis of the maximum supeeted eencontrations of W ese gases, he k en-site and off-site, was made. It was determined that tue maw 4== eameentration of these gases was well below he mar 4== permissibla coneantrations in restricted and unrestricted areas.
Armivsis of _h=4-- Canoantratlam #Amased The shalysis of the marimm eongentration of fispise Lases eat eeuld have been rolessed is based en (1) the volume of gar r ped through the leak and subsequently diffused through the earth, (2) W ===t=m commentretion of radioastivity cf tse relemmed gas, (3) the meteerelegical parameters ter Suttamis Equation for the site as given in the Final Safeguardo Repert, and (4) the metaal mean viad l velocity and direction la the valley of the asystown Esanch of he Jumista River reeestled during the period of %e leak.
The plant records indicate h at during the period of July, August, and september 1%3 me average imput rate to the gas desar tanks in the Radteagtive
- Waste Disposal Famility was 0.1 eubie feet par minute. Since no unusual operetiens
! were observed auring the period of someers there is no rences to mastans that a l higher than avessgo input rate esisted.
i l
Also, during the period of July, August, and September he roeords of the continuously recorded Staak Gas Detestar (RIC-3) indiaate that %e radioactivity I released tran all gas decay tanks, eroept for hoes oceassions when 2e tanks were knoen to oantain purged off-gases, was below the minimum detestable sensitivity of this detector. The Staak Gas Deteeter was salihasted wi% kneemt eensentretiens of ,
K 45 and the minissa detestable sensitivity van by the salibration surve for 1 ;
oount per second above boekground is 3 x microcuries per subio esatimeter.
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Gas doesy tank releases balaw the sensitivity of the staek detester have boom made during ammal operatism at potes between ene and seven suhis fed per mimata. These releases wors diluted by %e plant ventilating eyetam output of 15,000 suble feet per mimte prior te -nwant hy the Staak Oss Deteetor. The point where the gas doeay 4
tank release is mixed wi% he ventilating eyeten output is five fed frema the staek
! deteeter and sensequently it could be asemed Wt eenplete mixing does not oseur.
llowwver, a senservative mad == eeneantation based on a release rete af 2 subie feet per minute is used. This value, led to a ralsase m e of 0.1 subie feet pes-mimte yields a =dmum activity asse rate of 1 x mieresaries per second and o total release of radionetivity of less than 2 millieuries.
turing the period of eencom, the site wisul voleeity had a mesa value of 5 miles per hour with wind blowing fram the south-west. Using the maderate lapse rete
. cdeorological paremotors far Sutton's rquation detenmined for the site and givest in the Final f>afeguards Keports ami utilisity; button's Equation for a point soures at grourd laval W dihtion factor, at the controlled area fence 30 notere away trea the location of the lekk, in a north-easterly direetion, at an elevation of one meter from the ground, was found to be 5 5 x 10-9 YtzAs, for a release rute of 1 x 10-2 mieresuries per second the soneantration et the controlled area fanee, one meter above ground level, would be 5.5 x 10-11 mierocuries per subio sentimeter. This is apprezimately ens-tenWuaand2 the unrestricted area =d== pomissible sancentrations for Kr65 and Xe13).
In the case of pereennel within the santrolled trem W madam sensentassion i would occur 3 5 aders from a point eaures and 1 ader above the ground. This i e- ooneentration wuld have been 1 x 10-9 ue/oe which is below the MFC for a l 40 hour4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> work week. In the astual omse this area is not a nerarl weding area and no pereennel remained in tN area for more than a few mismates during the period being discussed. The assumption of a point sourse at ground level is overly conseavative since W metual gas bubbled up through ground wter, and then diffused upward through six feet of earth.
Osmalunion Based en the foregoing analyses, it is concluded that any unintentional release of redienstivity related to this inaident did not represent a possible unsafe condition relative to he operation of the facility or an unsafe situation with regard to any publie hasavd.
1 l' W . IL
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