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Category:ANNUAL OPERATING REPORT
MONTHYEARML20209C0051998-12-31031 December 1998 1998 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20248D7181997-12-31031 December 1997 1997 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20141C6661996-12-31031 December 1996 1996 Annual Rept for Saxton Nuclear Experimental Corp Facility ML20112C8451995-12-31031 December 1995 1995 Annual Rept for Saxton Nuclear Experimental Corp Facility 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 ML20045D7161992-12-31031 December 1992 1992 Annual Rept for Saxton Nuclear Experimental Corp. W/ 930622 Ltr ML20101L3341991-12-31031 December 1991 Experimental Corp 1991 Annual Rept. W/ ML20091D7351990-12-31031 December 1990 Facility 1990 Annual Rept ML20043D7261989-12-31031 December 1989 Experimental Corp 1989 Annual Rept. W/ 900531 Ltr ML20247B2821988-12-31031 December 1988 SNEC 1988 Annual Rept ML20206G0211986-12-31031 December 1986 Experimental Corp 1986 Annual Rept. W/ ML20141N5621985-12-31031 December 1985 Experimental Corp,1985 Annual Rept ML20214J2871985-12-31031 December 1985 Corrected Tables 1,2,3,5 & 6 to Saxton Nuclear 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 ML20073B5041983-04-0606 April 1983 Annual Rept for 1982 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. ML20085H6801970-02-28028 February 1970 Experimental Corp Operating Experience Rept for Sept 1969 - Feb 1970 ML20085D2281963-04-30030 April 1963 Reactor Plant Operating Experience Rept Apr 1962-1963 1998-12-31
[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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SAXTOli liUC1EAP rgircilD5f3AL CORI(l<ma CIEldTitJG EXPEy,7y);cg ILEIDRT Yor the teriw 08Pte.ilier 1, 1969 - Februar,Y 28, 1970
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413 1 SAXTOM !!UC19.h FJ.pDilm!IAL CO?JWTION k
k OPCtATING INSTitVCTION 413 IPJOEAR INSTR'RFNTATICC
- 2. Cond! t ions
- 1. The A.C. vital bus is energized.
1 II. Preeriutiens g 1.
Never renve both tource rance EF, channeh frca thnn service when a core 16 installed and the intermediate"rnngc chnnucle red lere 10-10 amps. i The DF3 high voltage must be turned off when the reactor is operat ng at pow'er levels above 1010 amps on int (mediate rance.
3.
If one power range channel fails while the reactor is in operation *tnd the channel will be deenergized for repairtThe reactor load will be held r:onntant.
be set for eingle channel operaticn. 6 III. Instructient . both ir.*.ormediat e range, and
- 1. For reactor startup, beth source rance.all three power t-e range chann 2.
prior to reactor startup the r.u: lear inrtrumentation 413 A-C. system must checked out in accordan e. with prmartup checkoff lists
' l ar
- a. for scram recovery or for startups boire made w f ing only instrumentation a modified checkoff may be used by per om those steps in h13 A-C which are marked 3*. ff b.
Far a series of tests or training startups,steps a modified in cheek-o may be used every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by perfoming only those b13 A-C which are marked 3 and those marked l ih
If the reactor startup is delayed and nore than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> have e aps from the last check-out, perform only those steps in h13 A-C wh are marked **. d cted d.
The prestartup checkoff of nuclear instrumentation must be con u by or directly supervised by a licensed reactor operator.
T hr n.inianum).
Allow sufficient wamup time (4 hre normal diat e,-
3 4.
During reactor startup closely monitor TSc the source and intemeriartup recor range level and startup rate indicatore.be switched as the to the higher i to
( 5. As neutron icvel is increatoc, ensure that an overla
' ' power rance channels.
T/:l
g .
10 25-63
' stnd.t 41312
- 6. k' hen the intennediate range neutron level exceeds 10-30 amps tur-off the BF3 high voltage. t
- 7. During startup when the m wer level reaches 10%, position the power level scram selector in IIIGli and shift from single channel to coincidence serarn. Check that 10% relays have operated to turn on
- the RATE SCRAM OFF lights on the Startup Rate Disconnect Panel.
- 8. k' hen operating at power levels of less than 10% place the power level scram selector in the ifW position and shift from coincidence to SINGII CHAlmEL.
- 9. During shutdown or after eergy tum on the BF3 high voltage when the intennediate range reads 10-w amps.
Sutraitted:M.$ d
~
Supervisor of Operations and Teste Approved e ,[ i 1[ t_ e*
'Iteactori 1[ra ~ Superintendent V g 5
a
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