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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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Text
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f SAXTON NUCLEAR EXPERIMENTAL CORPORATION DOCKET NO. 50-146 SUPPLEMCIT #1 to C11ANGE REQUEST #6
- 1. Applicant hereby submits Supplement #1 to Change Request #6 that
! vas filed on February 7,1963, in compliance with paragraph 3 of License DPR-4.
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N ;. y OJ SAXTON NUCLEAR EXPERIMENTAL CORPORATION p c~ 7 (3 \9#g /s/ R. E. Neidig M By 3 gh% $'
President g 4%8,gs$$#
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Attest:
(S E A L)
/s/R.E. Sypher Secretary Svorn and subscribed to before me this 22nd day of March 1963 (S E A L) /s/ Martin A. Kohr Notary Public Muhlenberg Township, Berks County My Commission Expires Feb. 4, 1966 9110150336 910424 PDR FOIA DEKOK91-17 PDR e .
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4
- arch 19, 1963 l' Docket No. 50-146 DPE-4 Technical Specifications Supplement #1 to Change Request #6 The following additional information and revision is submitted in support of Change Request f6:
N
- 1. The maximum calculated coal down rate of the main coolant system while N
at operating pressure at.d temperaturg vith a clean core and without I equilibrium Xenon and Samarium is 16 F/hr. This cool-down rate vould, of course, decrease with a decrease in the main coolant temperature below the operating temperature of 520 F and this cool-down rate would also decrease during core life as firsion product inventory is built up.
- 2. Approximately twelve hours n.ay be required to repack the tnree pistons of the triplex, reciprocating charging pumps. It is only necessary to repack one picton at a time and it is estimated that approxirantely four hours vill be required to repack one piston. These estimated times can be either longer or shorter, depending on the working conditions and the condition of the equipent at the time the work is carried out.
3 It may be necessary to use the safety injection system during this re-packing operation in the event that three conditions occur simultaneously.
It vould be necessary for both the standby or operable charging pump and the main coolant pump to fail during the period when the core is clean prior to the build-up of equilibrium Xenon and Samarium. This is a relatively short period during early core life. The estimated cool-down rate of 16 oF/hr. vill allow approximately four hours' time before the main coolant vould cool down to 450 F, wv ich is a condition equivalent to a shutdown margin in excess of 1% vith all the control rods fully inserted with zero boron. While the probability of these three events l occurring ut one time seems very small, in the event this series of events did occur simultaneously, it vill be possible to complete the repacking l of the pump piston being vork2d on in order to place thga pump back in service before the main ecolant temperature reaches 450 F.
(
' 4. The safety injection system would be used cnly in the remote event that the main coolant temperature reached h50 F or in the event that the main l
coolant temperature was dropping rapidly under the conditions described above. In the event it vould become necessary to use the safety injection system, vater containing 1200 pp boron could be pumped into the core intermittently by dropping the main coolant pressure to between 1700 and i 1800 psi. The safety injection system pumps vould operate in series under i this condition and since the pumps vould'be operating near their combined
! shut-off pressure of 1850 psi, the capacity of the pumps vould be con-siderably reduced below their rated capacity oi 375 gm. The capacity of l
these pumps in series at 1700 psi is approximately 240 g g . The total quantity of borated water that could be pumped into the system would be-limited by the free volume in the prescurizer which would be approximately 500 to 600 gallons as compared to a total main coolant system capacity of
-approximately 2500 gallons. Assuming complete mixing of 500 gallons of l vater containing 1200 pm of boron with the 2500 gallons of main coolant water, at essentially zero boron concentration, the average boron con-centration vould be approximately 200 pp and the average temperature l
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.4
.. ech 19, 1963
' Docket No. 50-146 DPR4 Technical Specifications Supplement #1 (page 2 of 2) to Change Requent #6 Under these conditions the reactor would vouldbeapproximately385}F.
be shut down by at least 2 % vith all control rods interted. Part ial mixing of the 1200 ppm borated water vonld result in either a higher boron concentration in the core or less dilution of temperature so that the shutdown margin vould be greater than Eff. This shutdown margin plus a slover cool-down rate at the lover main coolant temperatures vould provide en additional period of several hours to get one of the charging pumps back in service. Calculations show that with all centrol rods in-serted in the core and 200 pq in the coolant the reactcr vill be just critical at approximately 225 F.
While the use of the safety injection system to back up the charging pumps is expected to be a remote possibility as pointed out above, the use of this system under these co.ditions subjects the reactor vessel to stress conditions that are less severe than those for the loss of coolant accident that was analyzed for cyclic stresses and reported in Westinghouse Report WOAP-1620, " Supplementary Technical Infomation on the Saxton Reactor Vescel,"
5 Substitute the following paragraph for the paragraph under item 1, "Descrip-I tion of Change," in ChanSe Request No. 6:
Change item 12 on page 11 of the Saxton Technical Specifications as amended on October 9,1962 to read as follows:
i A charging system consisting of two motor-driven horitortal, triplex, reciprocating pumps, each having an adjustable capacity of 3 to 15 gpm at a total dynamic head of 2500 psig, is provided to charge degasified, demincralized make-up vater, concentrated borated vater, and water fram the purification system back into the main coolant system. These pumps vill be in operable condition during power operation of the reactor, except that one pump may be rendered i_noperable for the purpose of minor maintenance such as repacking the three piston packing C lands one at a time, so that the pump can be placed back in service within a period of four hours, if necessary. .One or both of these pumps will operate intemittently as required for the purification system, and for volume control of the main coolant system.
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