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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20134P3811996-11-25025 November 1996 Application for Amend to License DPR-4,submitting Decommissioning TSs ML20112A6771996-05-17017 May 1996 Application for Amend to License DPR-4,consisting of TS Change Request 58,revising Decommissioning TS ML20100F4851996-02-0202 February 1996 Application for Amend to License DPR-4,proposing Expansion of Permitted Principal Activities within the Exclusion Area Beyond Those Allowed by Current TS ML20094Q0551995-11-21021 November 1995 Application for Amend to License DPR-4,transferring All mgt- Related Responsibilities for Plant from SNEC to Gpun.Revised TS Encl ML20086A5681995-06-23023 June 1995 Addendum to TS Change Request 56 to License DPR-4,revising TS Pages 1,2 & 3 to Change Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee Maintained ML20084J3061995-06-0202 June 1995 Application for Amend to License DPR-4,proposing Changes to App a of TSs ML20078A2171995-01-12012 January 1995 Rev to TS Change Reqest 55 to License DPR-4,including Addl Text Resulting from Matl Provided in Response to Questions in NRC 950103 RAI ML20072C2341994-08-0808 August 1994 Application for Amend to License DPR-4,revising Content & Format of Existing TS & Analysis Applying Stds of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20045G7011993-06-23023 June 1993 TS Change Request 54 to License DPR-4,including Facility Characterization as Activity Permissible in TS ML20094P0301992-04-0202 April 1992 TS Change Request 53,Rev 3 to License DPR-4,removing Reactor Support Bldgs & Structures from TSs ML20235H0391987-09-22022 September 1987 Application for Amend to License DPR-4,consisting of Tech Spec Change 53 Re Removing Outbuildings & Structures ML20085H6591969-12-0202 December 1969 Amend 2 to Change Repts 15 & 16 to License DPR-4,describing Installation of Water Seal on Pressurizer Safety Valves & Spilled Coolant Recirculation Sys ML20085H6371969-11-24024 November 1969 Amend 9 to Change Request 32 to License DPR-4,clarifying Info Re Engineering Hot Channel Factors ML20085H6061969-11-20020 November 1969 Amend 8 to Change Request 32 to License DPR-4,revising Emergency Preparedness Plan.Plan Encl ML20085H5951969-10-27027 October 1969 Amend 7 to Change Request 32 to License DPR-4 Re LOCA Prevention & Protection ML20085H4981969-10-0303 October 1969 Amend 6 to Change Request 32 to License DPR-4,revising Limiting Condition for Operations Re Concentration of Radioactivity in Refueling Water Storage Tank ML20085H4681969-07-0808 July 1969 Amend 1 to Change Rept 16 to License DPR-4,describing Mods to Safety Injection Sys & Installation of Automatic Long Term Coolant Recirculation Sys ML20085H3751969-07-0808 July 1969 Amend 1 to Change Request 15 to License DPR-4,describing Changes to Pressurizer Safety Relief Valves Installation ML20085G2311969-04-29029 April 1969 Application for Interim Amend to License DPR-4 & Change Request 33,authorizing Low Power Operation ML20085G1111969-04-0101 April 1969 Amend 2 to Change Request 32 to License DPR-4,requesting Interim Authority to Load Core III Fuel ML20085G2081969-04-0101 April 1969 Amend 3 to Change Request 32 to License DPR-4,submitting Rept Entitled, Summary Rept on Buckling of Saxton Core II Fuel Assemblies & Prevention of Buckling in Core III ML20085G0911969-03-19019 March 1969 Application for Amend to License DPR-4,requesting Interim Authority to Load Core III Fuel ML20085G0711969-03-12012 March 1969 Amend 1 to Change Request 32 to License DPR-4,reevaluating Core III LOCA ML20085G0471969-01-0707 January 1969 Application for Amend to License DPR-4,extending Expiration Date to 721231 ML20085F9891968-11-13013 November 1968 Change Rept 15 to License DPR-4,describing Mods to Pressurizer Safety Relief Valve Installation ML20091D1381968-08-30030 August 1968 Addendum to Change Request 32 to License DPR-4,submitting WCAP-7219 Rept Re Addendum to License Application ML20085F6241968-04-19019 April 1968 Amend 1 to Change Request 31 to License DPR-4 Re Fuel Bearing Rods ML20085F6011968-03-0404 March 1968 Change Request 31 to License DPR-4 Re Test Fuel Assemblies ML20085F5671968-02-0202 February 1968 Change Request 30 to License DPR-4 Re Test Fuel Assemblies ML20085F5571967-11-21021 November 1967 Amend 3 to Change Request 25 to License DPR-4 Re Testing of Safety Valves ML20085F5341967-10-10010 October 1967 Amend 2 to Change Request 25 to License DPR-4 Re Permissive Switch,Variable Frequency Motor Generator Set Mods & Safety Injection Sys Flow Totalizer ML20085F5271967-10-10010 October 1967 Change Rept 14 to License DPR-4,revising Supercritical Technology Program ML20085F5191967-09-20020 September 1967 Change Request 13 to License DPR-4 Re New Rod Oscillator ML20085F5121967-09-0606 September 1967 Amend 1 to Change Request 27 to License DPR-4 Re Ph Range During Testing ML20085F5011967-08-31031 August 1967 Change Request 29 to License DPR-4 Re Test Fuel Subassemblies ML20085F4871967-08-28028 August 1967 Change Request 28 to License DPR-4 Re Test Fuel Subassemblies ML20085F4611967-08-0303 August 1967 Change Request 27 to License DPR-4 Re Test Fuel Subassemblies ML20085F4181967-06-27027 June 1967 Amend 1 to Change Request 25 to License DPR-4 Re Upper Limit Accident Results Calculations ML20085F2781967-04-24024 April 1967 Change Request 26 to License DPR-4,lowering Settings of PSV-1 & PSV-2 to Max Value of 3,980 Psig ML20085F1741966-07-28028 July 1966 Change Request 24 to License DPR-4 Re Two Test Fuel Subassemblies ML20085F1411966-06-22022 June 1966 Change Request 23 to License DPR-4 Re Test Fuel Subassemblies ML20085E9341966-02-24024 February 1966 Change Request 22 to License DPR-4 Re Two Test Fuel Subassemblies for Testing ML20085E8711965-08-0202 August 1965 Change Request 21 to License DPR-4,changing Control Rods ML20085E6861965-05-0707 May 1965 Change Request 18 to License DPR-4 Re Fuel & Cladding Development ML20085E6941965-05-0707 May 1965 Change Request 20 to License DPR-4 Re Composition of Fuel Assemblies ML20085E6691965-04-0202 April 1965 Change Request 17 to Tech Specs & Amend 16 to License DPR-4, Authorizing Receipt,Possession & Use of Plutonium Fueled Subassemblies ML20085E6651965-04-0202 April 1965 Change Request 19 to Tech Specs & Amend 17 to License DPR-4, Authorizing Receipt,Possession & Use of Plutonium as Fuel in Partial Loading of Reactor ML20085D9231965-03-0505 March 1965 Rev 1 to Change Request 16 to Application for Amend to License DPR-4,revising Safeguards Rept ML20085D8661964-11-10010 November 1964 Change Rept 12 to Application for Amend to License DPR-4, Replacing Experimental Fuel Subassembly W/Subassembly Containing Nine Std Fuel Rods ML20085D7561964-10-0808 October 1964 Change Request 16 to Application for Amend to License DPR-4, Revising Supercritical Technology Program.Safeguards Rept Encl 1996-05-17
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217A9761998-04-20020 April 1998 Amend 15 to License DPR-4,allows Decommissioning of Saxton Nuclear Experimental Corp Facility ML20134P3811996-11-25025 November 1996 Application for Amend to License DPR-4,submitting Decommissioning TSs ML20112A6771996-05-17017 May 1996 Application for Amend to License DPR-4,consisting of TS Change Request 58,revising Decommissioning TS ML20100F4851996-02-0202 February 1996 Application for Amend to License DPR-4,proposing Expansion of Permitted Principal Activities within the Exclusion Area Beyond Those Allowed by Current TS ML20094Q0551995-11-21021 November 1995 Application for Amend to License DPR-4,transferring All mgt- Related Responsibilities for Plant from SNEC to Gpun.Revised TS Encl ML20086A5681995-06-23023 June 1995 Addendum to TS Change Request 56 to License DPR-4,revising TS Pages 1,2 & 3 to Change Organization Performing Remainder of Characterization Activities & Future Decommissioning Activities to Assure Linkage W/Licensee Maintained ML20084J3061995-06-0202 June 1995 Application for Amend to License DPR-4,proposing Changes to App a of TSs ML20078A2171995-01-12012 January 1995 Rev to TS Change Reqest 55 to License DPR-4,including Addl Text Resulting from Matl Provided in Response to Questions in NRC 950103 RAI ML20072C2341994-08-0808 August 1994 Application for Amend to License DPR-4,revising Content & Format of Existing TS & Analysis Applying Stds of 10CFR50.92 in Making Significant Hazards Considerations Determination ML20045G7011993-06-23023 June 1993 TS Change Request 54 to License DPR-4,including Facility Characterization as Activity Permissible in TS ML20094P0301992-04-0202 April 1992 TS Change Request 53,Rev 3 to License DPR-4,removing Reactor Support Bldgs & Structures from TSs ML20235H0391987-09-22022 September 1987 Application for Amend to License DPR-4,consisting of Tech Spec Change 53 Re Removing Outbuildings & Structures ML20085H6591969-12-0202 December 1969 Amend 2 to Change Repts 15 & 16 to License DPR-4,describing Installation of Water Seal on Pressurizer Safety Valves & Spilled Coolant Recirculation Sys ML20085H6371969-11-24024 November 1969 Amend 9 to Change Request 32 to License DPR-4,clarifying Info Re Engineering Hot Channel Factors ML20085H6061969-11-20020 November 1969 Amend 8 to Change Request 32 to License DPR-4,revising Emergency Preparedness Plan.Plan Encl ML20085H5951969-10-27027 October 1969 Amend 7 to Change Request 32 to License DPR-4 Re LOCA Prevention & Protection ML20085H4981969-10-0303 October 1969 Amend 6 to Change Request 32 to License DPR-4,revising Limiting Condition for Operations Re Concentration of Radioactivity in Refueling Water Storage Tank ML20085H4681969-07-0808 July 1969 Amend 1 to Change Rept 16 to License DPR-4,describing Mods to Safety Injection Sys & Installation of Automatic Long Term Coolant Recirculation Sys ML20085H3751969-07-0808 July 1969 Amend 1 to Change Request 15 to License DPR-4,describing Changes to Pressurizer Safety Relief Valves Installation ML20085G2311969-04-29029 April 1969 Application for Interim Amend to License DPR-4 & Change Request 33,authorizing Low Power Operation ML20085G2081969-04-0101 April 1969 Amend 3 to Change Request 32 to License DPR-4,submitting Rept Entitled, Summary Rept on Buckling of Saxton Core II Fuel Assemblies & Prevention of Buckling in Core III ML20085G1111969-04-0101 April 1969 Amend 2 to Change Request 32 to License DPR-4,requesting Interim Authority to Load Core III Fuel ML20085G0911969-03-19019 March 1969 Application for Amend to License DPR-4,requesting Interim Authority to Load Core III Fuel ML20085G0711969-03-12012 March 1969 Amend 1 to Change Request 32 to License DPR-4,reevaluating Core III LOCA ML20085G0471969-01-0707 January 1969 Application for Amend to License DPR-4,extending Expiration Date to 721231 ML20085F9891968-11-13013 November 1968 Change Rept 15 to License DPR-4,describing Mods to Pressurizer Safety Relief Valve Installation ML20091D1381968-08-30030 August 1968 Addendum to Change Request 32 to License DPR-4,submitting WCAP-7219 Rept Re Addendum to License Application ML20085F6241968-04-19019 April 1968 Amend 1 to Change Request 31 to License DPR-4 Re Fuel Bearing Rods ML20085F6011968-03-0404 March 1968 Change Request 31 to License DPR-4 Re Test Fuel Assemblies ML20085F5671968-02-0202 February 1968 Change Request 30 to License DPR-4 Re Test Fuel Assemblies ML20085F5571967-11-21021 November 1967 Amend 3 to Change Request 25 to License DPR-4 Re Testing of Safety Valves ML20085F5341967-10-10010 October 1967 Amend 2 to Change Request 25 to License DPR-4 Re Permissive Switch,Variable Frequency Motor Generator Set Mods & Safety Injection Sys Flow Totalizer ML20085F5271967-10-10010 October 1967 Change Rept 14 to License DPR-4,revising Supercritical Technology Program ML20085F5191967-09-20020 September 1967 Change Request 13 to License DPR-4 Re New Rod Oscillator ML20085F5121967-09-0606 September 1967 Amend 1 to Change Request 27 to License DPR-4 Re Ph Range During Testing ML20085F5011967-08-31031 August 1967 Change Request 29 to License DPR-4 Re Test Fuel Subassemblies ML20085F4871967-08-28028 August 1967 Change Request 28 to License DPR-4 Re Test Fuel Subassemblies ML20085F4611967-08-0303 August 1967 Change Request 27 to License DPR-4 Re Test Fuel Subassemblies ML20085F4181967-06-27027 June 1967 Amend 1 to Change Request 25 to License DPR-4 Re Upper Limit Accident Results Calculations ML20085F2781967-04-24024 April 1967 Change Request 26 to License DPR-4,lowering Settings of PSV-1 & PSV-2 to Max Value of 3,980 Psig ML20085F1741966-07-28028 July 1966 Change Request 24 to License DPR-4 Re Two Test Fuel Subassemblies ML20085F1411966-06-22022 June 1966 Change Request 23 to License DPR-4 Re Test Fuel Subassemblies ML20085E9341966-02-24024 February 1966 Change Request 22 to License DPR-4 Re Two Test Fuel Subassemblies for Testing ML20085E8711965-08-0202 August 1965 Change Request 21 to License DPR-4,changing Control Rods ML20085E6941965-05-0707 May 1965 Change Request 20 to License DPR-4 Re Composition of Fuel Assemblies ML20085E6861965-05-0707 May 1965 Change Request 18 to License DPR-4 Re Fuel & Cladding Development ML20085E6691965-04-0202 April 1965 Change Request 17 to Tech Specs & Amend 16 to License DPR-4, Authorizing Receipt,Possession & Use of Plutonium Fueled Subassemblies ML20085E6651965-04-0202 April 1965 Change Request 19 to Tech Specs & Amend 17 to License DPR-4, Authorizing Receipt,Possession & Use of Plutonium as Fuel in Partial Loading of Reactor ML20085D9231965-03-0505 March 1965 Rev 1 to Change Request 16 to Application for Amend to License DPR-4,revising Safeguards Rept ML20085D8661964-11-10010 November 1964 Change Rept 12 to Application for Amend to License DPR-4, Replacing Experimental Fuel Subassembly W/Subassembly Containing Nine Std Fuel Rods 1998-04-20
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SAXTON tNCLEAR EXPERIMENTAL CORPORATION DOCKET NO. 50-lh6
- LICENSE DPR-b CHAN3E REPORT #10
- 1. Applicant hereby submits Change Report #10 in conpliance with paragraph 3(B)(1) of License TER-h. This chango pertains to the installation of a filter in the purification system which was described in Subsection 207 of the Saxton Final Safeguards Report.
Pages 207.2 and 207.3, revisrd as of June b,1963, and figure 207-1, revised as of May 6, 1963, are attached to tnis Change Report #10.
SAXTON tWCLEAR EXPDlIMENTAL CORPORATION Dy /s/ R. E, Ne$ die Fresident Attests (S E A L) /ej/ R. E. Sypher ,
Secretary Sworn and taubscribed to besfore me this 10th day of June 1963
- 3.,
7: . ' / , ~; .
/s/ Charles J. Ausel f(' Notary Public
'O (S E A L)
Muhlenberg Township, Berks County
- My Commission Expires Oct. lb, 1966
(
l 9110150370 910424 PDR FOIA DEKOK?1-17 PDR IG 11.
+
June h, 1963 Docket No. 50-lh6 DPR-L ,
Change Report #10 ;
- 1. Descriplien of Change A nine-element filter unit and by-pass valving has been installed in the purification system in series with, and just ahead of the existing demineralizer post filter. Revised pages 207 2, 207 3, dated June h, 1963, !
and a revised Figure 207-1, dated May 6,1963, of the Saxton Final Safe-guards heport are attached to reflect this change.
- 2. Purport of Charge This added filter has a significantly larger area than the existing filter in order to facilitate the removal of solids from the main coolant nystem during system cican-ups.
3 Operating Proceduro The valving of the filters is arranged to permit both filters to be operated in series, the initially installed single-elettent filter to be operated alone, or both filters by-passed. During ciern-up operations l
' the filters will be operated in series. During normal operation the new nire-element filter may be by-passed.
l
- h. Conclusion l-l It is our conclusion that this change does not involve a change in the Technical Specifications or any unreviewed safety question and that the health and safety of the public will not be endangered by this change.
1 1
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207 2 the water passes through the purificatier. demineralizer during normal The cperation, or through the boric acid demineralizer after feed and bleed.
soluble corrosion products in the water are removed by ion exchange, and The the insoluble products are removed by the filter action of *ae resin bed.
demineralizer versels are installed as permanent units with provision for sluicing spent resins to the radioactive waste disposal facility. Sampling lines are provided both upstream and downstream of the domineralizers so that an indication of dcmineralizer efficiency can be obtained.
From the demineralizer, the purification water flows to the system post filters. During main coolant system clean-up operations the demineralizer The first filter, a nine-may be by-passed and both filters operated in series.
c1cnent, disposable type cartridge unit is used to remove solids which would otherwise rapidly clog the second filter, a singic-element unit which contains a porous, stainless steel element. During normal operation, the nine-element unit may be by-passed and the single-element unit used to remove any resin fines or other insoluble corrosion products which carry over from the demineralizers. FYom the filters the water is piped outside of the containment A vessel to the surge tank located in the control and auxiliary building.
hydrogen gas supply system is provided to maintain The surgea tank hydrogen sprayoverpressure nozzle spraysof approximately 15 psig in the surge tank.
the incoming water into the hydrogen atmosphere in the surge tank, where the hydrogen gas is absorbed by the water thereby providing corrosion inhibition.
In order to prevent an explosive mixture of hydrogen and oxygen from occurring in the surge tank, a nitrogen gas supply is provided to sweep the tank.
I Make-up water from the secondary plant is added at the surge tank through a valve that can be operated from the main control room. Chemicals required for plant operation are also added at the surge tank through the make-up water line. During the feed and bleed operation, water is discharged to the radioactive waste disposal facility through a manually operated valve.
The water flows from the surge tank into the charging system where i
' boric acid may be added from the chemical addition system and whereWhen the water the is pumped it.to the high }. essure line to the main coolant system.
reactor is operating at power, the pressurized water is passed through the shell side of the regenerative heat exchanger where it is heated to prevent thermal l
shock on the main coolent piping connection and it then is returned to the main coolant loop at the cold leg downstream of the main coolant circulating pump.
During hot shutdown, the purification system nonregenerative heat exchanger is used to remove decay heat. In addition, this 0 heat exchanger is used to reduce the main coolant water temperature to 300 F prior to placing the shutdown cooling system in operation. During these shutdown operations, the regenerative heat exchanger can be partially by-passed by three-way valve TIC-2hV which l
operates on a signal from T10-2h to automatically maintain the regenerative heat exchanger tube side outlet water temperature below 3000F.
C. Components
- 1. Regenerative Heat Dcchanger This unit is a horizontally mounted U-tute and abell type heat ex-changer. The tabes are welded to the tube sheet and the end closure is of a welded cap design. The tubes and all other material in contact with the main coolant water are Type 30h stainless s teel. The regene:.*ative neat exchangar $s designed for 2750 psig pr essure so thnt the relief valvo provided on the shc11 side of the heat exchanger may be set at a higher presstre than the main coolant safety valves, thereby allowing the :vessure of the main loop to be controlled
207 3 I
The unit is sized to remove b,500,000 Btu /hrwithatubeside inlet tempercture of 5200F, a tube side outlet temperature of 2h5DF, and a chell side inlet comperature of 1250F. ,
t
- 2. Let-Down Flow Control Valve The let-down flow control valva is designed to control the flow through the purification system so that a constant average level is maintained in the pressurizer. It is a disphraps operated valve designed for 2000 psi at 5500F and a maximum open flow rate of 38 gpm.
- 3. Honregenerative Heat Fachanger This heat exchanger is a flanged head, horizontal, U-tubs and shell type unit. The tubes and all other surfaces in contact with the main coolant are Type 30h stainless steel. The ahen side and tube side of this unit are designad for 150 peig at 3000F. A liquid relief valve is provided on the shell side of the unit in accordance with code requirements.
The unit is designed to transfer heat at a rate of 1,800,000 Btu /hr with a tube side inlet temperature of 2h50F, a tube side0 outlet temperature of 1250F, and a shell side inlet temperature of 100 F.
- h. Demineralizers Both domineralizer vessels are constructed of Type 30h stain-The design pressure for the less steel and contain 6 cubic feet of resin.
vessel shells is 150 psig at 3660F, The purification demineralizer contains a mix-ture of cation and anion resins containing one equivalent of lithium ions for each equivalent of hydroxide ions. The total exchange capacity of the unit is 72 kilograma expressed as calcium carbonate. The boric acid demineralizer contains an I anion resin which is in the OH form. The total exchange capacity of the unit is approximately 26 pounds of boric acid.
i l 5. Filter I Two filters are provided; a nine-element disposable cartridge type unit followed by a single-e3 nment unit. The bodies of both filtersTne are 300 Series stainless steel capable of withstanding 150 psi and 200 F.
nine-element filter elements are twisted fiber cartridges with stainless steel backup screens. The single-element filter uses a porous stainless steel element.
- 6. Surge Tank This tank is constructed of Type 30h stainless steel and is designed for 150 psig and 366"F. It is of all welded construction with the exception of the manhole which is flanged.
The tank has a volume of 75 cubic feet and is designed to contain that volume of water which is accumulated there during the maximum temperature rise in the main coolant system during normal plant operation.
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