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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20236N9161998-04-30030 April 1998 Rev 2 to Wmg 9801-7025, Saxton Reactor Pressure Vessel & Internals Final Characterization ML20236N9101998-03-31031 March 1998 Rev 1 to Wmg 9803-7025, Saxton SG & Pressurizer Characterization. W/Supporting Documentation from Reactor Vessel Package ML20210Q2321997-08-31031 August 1997 Rev 1 to Updated SAR for Decommissioning SNEC 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 ML20115K0821995-05-11011 May 1995 1994 Saxton Soil Remediation Project Rept ML20056G8241993-08-31031 August 1993 Penelec/Gpu Internal Affairs Dept Williamsburg Incident Investigation 89-WM-2 ML20101R2641992-03-31031 March 1992 Redacted Version of Penelec/Gpu Internal Affairs Dept Rept Williamsburg Incident Investigation 89-WM-2 ML20085C5901991-10-0404 October 1991 Rev 1 to Safeguards Rept for Saxton Core III 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 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 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 ML20078A2881972-04-30030 April 1972 Analysis of Effects of Flooding on Saxton Containment Vessel ML20085G1041969-04-0101 April 1969 Summary Rept on Buckling of Saxton Core II Fuel Assemblies & Prevention of Buckling in Core III ML20085F9741968-08-31031 August 1968 Safeguards Rept for Saxton Core III ML20085F9421968-06-10010 June 1968 LOCA Prevention & Protection ML20085F5281967-10-10010 October 1967 Revised Pages for Safeguards Rept for Supercritical Technology Program ML20085F1821966-12-31031 December 1966 Safeguards Rept for Saxton Reactor Operating at 35 Mwt ML20085E8201965-05-31031 May 1965 Suppl 1 to Safeguards Rept for Saxton Reactor Partial Plutonium Core II ML20085E6551965-03-31031 March 1965 Safeguards Rept for Saxton Reactor Partial Plutonium Core II ML20085D9091965-02-28028 February 1965 Suppl 1 to Safeguards Rept for Supercritical Technology Program of Saxton Nuclear Experimental Corp 5-Yr R&D Program ML20085D7601964-10-31031 October 1964 Safeguards Rept for Supercritical Technology Program of Saxton Nuclear Experimental Corp 5-Yr R&D Program ML20085D7891964-10-31031 October 1964 Suppl 1 to Addendum 4 to Safeguards Rept for Phase I of Saxton Nuclear Experimental Corp 5-Yr R&D Program ML20085G0111964-04-13013 April 1964 Containment Vessel Leakage Rate Test Absolute Method ML20085D6761964-03-31031 March 1964 Addendum 3 to Safeguards Rept for Phase I of Saxton Nuclear Experimental Corp 5-Yr R&D Program ML20085D3821963-10-31031 October 1963 Addendum 2 to Safeguards Rept for Phase I of Saxton Nuclear 5-Yr R&D Program ML20085D0521962-12-20020 December 1962 Addendum 1 to Safeguards Rept for Phase 1 of Saxton Nuclear Experimental Corp 5-Yr R&D Program ML20085C8401962-04-25025 April 1962 Field Dye Penetrant Insp of Saxton Reactor Vessel ML20085C5081961-04-20020 April 1961 Final Safeguards Rept 1998-04-30
[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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Revised Pages for Safeguards Report for the Supercritical Technology Program s
9110;?O201 910^24 POR FOIA DEKOK91-17 PDR %{g>'j;i
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These revised pages incorporate modifications to the Supercritical loop as described in the Safeguards Report A. Safenuards Report for the Supercritical Technology Program
- 1. Revised page II-2: 1 The high pressure gas compressor has been relocated to the C&A ,
building to allow accessability for maintenance.
- 2. Revised page II-4: IJ The coolant leakage is piped through a filter to the deaerator via the systrs:1 collection header for return to the loop. This provides for chemistry control of the returned water by the duJrator.
3 hevised page 11-5: 2 LI-X4 has been deleted.
- 4. Revised pages II-5: 3 and added page II-5: ha This reflects the addition of a coolant reservoir refill tank. The addition of this tank permits remote refilling of the coolant reservoir while the loop is in operation' and access to the containment is restricted.
- 5. Revised page II-5 5 Reflects change in relief valves set pressures per Change No. 26.
- 6. Revised page II-5: 7 Each sample stream flows through a sample cooler, then through a pressure reducing restriction into a mixed bed sample ion exchanger. l The sample pressure reducing valves have been replaced by capillary tubing restrictions to eliminate the uncertainity of letdown valve operational reliability for such low volume flows.
- 7. Revised page II-6: 1 Changed the vacuum pump seal water reservtAr drain from the deaerator to the discharge tank.
1
- 8. Revised page II-6: 2 A low pressure supply of air is provided, as required, to provide an .
ex:cus of ozygen for recombination of any excess hydrogen produced.
In addition, a sampic point is provided in the discharge line from the vapor container to periodically ammple the off-gases from the loop.
l
- 9. Revised page II-7 1 Reflects changes to heater controller, QC-X1. The signals from flow controller, FRC-X1; heater inlet tnmperature recorder, THC-Il0; and the heater power recorder, QRC-X3 have been eliminated. This leaves the temperature control system dependent only on the output temp-erature of the heater and is not affected by variations from flow recorder-controller, FRC X1. The comparison part of the control w! ich cunpared thermal output of the heater with electrical power used by the heater has been eliminated. It served no usefbl purpose and was a unnecessary part of the control system.
- 10. Revised page II-7: 2 Reflects a change in the control function of flow controller, FRC X1.
Flow is no longer automatically controlled by temperature va-iations in the pressure tube, but is an independent variable controlled by a set point value in the controller. The total heat generated $". che fuel assembly, canpared to the total in the loop, is so small that adjusting flow to vary with fuel outlet temperature serves no useful function.
- 11. Revised page II-7 3 Reflects change in the control function of flow controller, FRC-X1, during partial loss-of-flow accident. The flow set points that define the accident are intended to protect the experiment. Flow is now independent of temperature variations and will be set by design calculations prior to operation.
- 12. Revised page II-7: 4 Reflects change in control ihnetion of loop flow controller FRC-Il during total loss of flow accident. The loop flow controller now functions as an independent variable as does temperature and pressure.
In the loss-of-f)ow accident the pressure control valve PRC-X6 continues to act as a pressure control valve. As soon as the flow is stopped, the loop starts to depressurize and PRC-I6 begins to close
. .__ _ _ . _ ._ ~. _ _ _ _ _ _ . ___ . _ . _ - _ _ . _ _ _ _ _ ___
. l l
l while the loop flow controller; FRC X1 centinues to act as a flow controller. The loop panpAby-pass valve therefore continues to total flow blockage is prevented by a receive a control signal.
mechanical limit on the pressure control valve PRC-X6. This-prevents the valve from closing beyond the minimum flow requirement for cooling of the experimental fuel.
13 Revised page II-7: 5 Reflects change in the control function of loop pressure controller, PRC X6. The pressure controller, PRC-X6, maintains pressure control of the loop during a loss-of-flow energency. The flow controller, FRC-X1, no longer takes over this function as previously described.
The purpose of this change is to maintain control of both flow and pressure during the emergency and not increase the rate at which the loop would tend to depressurize. Operating PRC-X6V as a flow control would increase the rate of depressurization by opening the valve in attempting to maintain flow. ,
- 14. Revised page 11-7: 6 Control function of TRC X4 has been deleted.
- 15. Revised page II-7: 9 A burnout feature has been added tauperature recorder TR Il-12.
- 16. Revised page II-7: 15 Reflects changes in the control function of deaerator level controller, llc-X3.
- 17. RevisM page II-7: 16 The by-pass valves HC-X21 and HC-X22 have been removed from the system to reduce potential loop operational difficultir; 7uch as leakage of split body valves at supercritict ' conditions.
- 18. Revised pages III-1: 1 and III-1: 2 Reflects changes in the loop startup procedure.
19 Revised page III-2: 1 Reflects changes in loop operation at supercritical pressure and temperature. The loop flow is now preset at a fixed value and the heater power is variec according to the fuel outlet temperature.
With only one variable, temperature control will be easier and less subject to instruments hunting for a control point. In addition, power calculations for the fuel will be much simpler with a fixed flow. To prevent starving the fuel, preset set points turn off the heater on low flow and scram the reactor on loss-of-flow.
- 20. Revised page III-3: 1 Reflects changes in the loop shutdown procedures.
- 21. Revised page III-4: 3 Reflects changes to the loop cleanup and decontamination procedures.
- 22. Revised page III-5: 1 Reflects change in the function of loop pressure control valve, PRC-X6V on loss of flow.
- 23. Revised Figures 1 and 2.
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