Letter Sequence Request |
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MONTHYEARML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr Project stage: Request ML20155G1661988-09-23023 September 1988 Forwards Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purpose of Sampler Analysis or Instrument Calibr.Fee Paid Project stage: Request ML20206K4011988-11-18018 November 1988 Informs That Portions of 880923 Application for Amend to License DPR-36 Not in Compliance W/Regulations.Portions Rejected from Consideration Include:Deletion of Cover Ltr, Notice of Issuance & B-50 Agreement Project stage: Other ML20245C4921989-04-18018 April 1989 Forwards Amend 70 to License DPR-34 & Safety Evaluation. Amend Changes Amount of Radioactive Matls Licensee May Possess for Purpose of Sample Analysis or Instrument Calibr Project stage: Approval 1988-09-23
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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 ML20151S2411988-04-20020 April 1988 Application for Amend to License DPR-34,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery & Associated Battery Charger Disconnected from Dc Bus ML20151R8141988-04-20020 April 1988 Application for Amend to License DPR-34,deleting 10CFR51.5(b)2 ML20149M2851988-02-0808 February 1988 Application for Amend to License DPR-34,revising Tech Specs Re Plant Protective Sys Trip Setpoints & Operating Requirements ML20149N0371988-02-0505 February 1988 Application for Amend to License DPR-34,changing Administrative Controls to Reflect Organizational Changes ML20238C3431987-12-23023 December 1987 Application for Amend to License DPR-34,revising Tech Specs Re safety-related Cooling Sys,Per 871202-03 meetings.W/re- Drafted Tech Specs & Discussions of NRC Comments from Aug 1987 & 871202-03 Meetings ML20236C6271987-10-15015 October 1987 Application for Amend to License DPR-34,deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements from Tech Specs ML20235W8521987-10-0101 October 1987 Application for Amend to License DPR-34,revising Tech Spec Sections Elco 8.1.1 to Clarify Actions on Inoperble Halogen Monitors & ESR 8.1.1 & 8.1.2 to Clarify Conditions Re Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20216H7221987-06-25025 June 1987 Application for Amend to License DPR-34,changing Tech Spec Limiting Condition for Operation 4.1.9 to Reduce Potential for Flow Stagnation & Prevent Excessive Fuel Temps in Core & Spec 5.1.8 to Incorporate Associated Requirements ML20210B6831987-04-23023 April 1987 Application for Amend to License DPR-34,changing Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys.Fee Paid ML20206P3811987-04-0808 April 1987 Application for Amend to License DPR-34,revising Interim Tech Spec 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserved Shutdown Sys,Per Rev 4 to FSAR ML20207Q5381987-01-21021 January 1987 Application to Amend License DPR-34,changing Tech Specs for Limiting Condition for Operation 4.6.1, Auxiliary Electric Sys, to Bring Consistency to Electrical Sys Nomenclature. Fee Paid ML20207P9891987-01-15015 January 1987 Application for Amend to License DPR-34,requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of Operable HXs ML20207D1891986-12-23023 December 1986 Application for Amend to License DPR-34,revising Tech Specs to Delete Snubber Tables & Correct Typos 1997-04-03
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20141K9941997-05-0505 May 1997 Amend 89 to License DPR-34,designating All Elements of Approved Decommissioning Plan as License Termination Plan ML20137L1041997-04-0303 April 1997 Requests Termination of Facility Operating License DPR-34, Per 10CRF50.82(a)(9) ML20134K4591996-11-0707 November 1996 Requests That NRC Terminate Facility Operating License for Plant,Per 10CFR50.82(a) ML20082K2271995-04-14014 April 1995 Application for Amend to License DPR-34,revising Decommissioning TS to Reflect Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3251993-05-18018 May 1993 Application for Amend to License DPR-34,changing TS to Impose More Restrictive Leak Test Acceptance Criteria for Reactor Bldg Ventilation Sys HEPA Filters to Permit Use of Graphite Handling Alternatives to Minimize Exposures ML20118B2121992-09-25025 September 1992 Supplemental Application for Amend to License DPR-34, Changing Decommissioning TS to Clarify & to More Accurately Reflect Decommissioning Conditions ML20096H1881992-05-19019 May 1992 Suppl to 920319 Application for Amend to License DPR-34, Requesting Early Consideration of Decommissioning TS Provision That Deletes Current Limitations on Temp of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys ML20094L2781992-03-19019 March 1992 Application for Amend to License DPR-34,revising TS to Provide Controls & Limits Appropriate for Decommissioning ML20086T1181991-12-24024 December 1991 Application for Amend to License DPR-34,changing TS to Revise Mgt Titles to Reflect Reorganization in Jan 1992, Deleting Programs No Longer Necessary After Nuclear Fuel Removed & Deleting Requirements for Technical Advisors ML20086C5271991-11-15015 November 1991 Supplement to 911011 Application for Amend to License DPR-34 Changing Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps to Correct Page Numbering ML20091D7591991-10-11011 October 1991 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.2.15 to Permit Operation of Prestressed Concrete Reactor Vessel Liner Cooling Water Sys at Somewhat Lower Temps than Currently Specified ML20082L9281991-08-30030 August 1991 Application for Amend to License NPF-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning ML20066A3741990-12-21021 December 1990 Application for Amend to License DPR-34,changing Tech Specs to Provide Controls & Limits Appropriate for Decommissioning,Per Generic Ltr 89-01 ML20059L5871990-09-14014 September 1990 Application for Amend to License DPR-34,changing Tech Spec Design Feature Section 6.1,by Removing CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20055G7091990-07-20020 July 1990 Application for Amend to License DPR-34,revising Tech Spec 6.1 to Remove Equipment to Support Plant Closure ML20043F7461990-06-0606 June 1990 Application for Amend to License DPR-34,revising Physical Security Plan to Reflect Permanent Shutdown of Facility & Plant Conditions During Defueling.Encls Withheld (Ref 10CFR73.21) ML20042F3141990-04-26026 April 1990 Application for Amend to License DPR-34,providing Tech Spec Changes Needed to Complete Defueling ML20006B7841990-01-25025 January 1990 Application for Amend to License DPR-34,adding Nuclear Training & Support Manager to Nfsc Membership ML19332E8831989-12-0404 December 1989 Application for Amend to License DPR-34,supplementing Proposed Tech Spec Re Reactivity Control ML19332F3531989-12-0404 December 1989 Supplemental Application for Amend to License DPR-34, Changing Tech Spec Sections 4.7 & 5.7, Fuel Handling & Storage. ML20006C5141989-11-21021 November 1989 Application for Amend to License DPR-34,restricting Reactor Operation at Any Power Level & Deleting Paragraph 2.D.(4) Which Authorizes Operation Above 2% Power After 900630 ML19327B1311989-10-13013 October 1989 Application for Amend to License DPR-34,deleting Limiting Conditions for Operation 4.12 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding New Reactivity Control Section to Supersede Interim Tech Specs ML19351A3261989-10-13013 October 1989 Application for Amend to License DPR-34,revising Tech Spec 6.1 Re Defueling Phase Document Design Features ML20248G3191989-10-0101 October 1989 Application for Amend to License DPR-34,modifying License Condition to Include Statement That Facility Will Not Be Oeprated for Electric Power Production After 890818 ML20248G4431989-09-30030 September 1989 Application for Amend to License DPR-34,changing Limiting Condition for Operation 4.4.7 & 4.4.8 & Surveillance Requirements 5.4.14 & 5.4.15 Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247G7761989-09-14014 September 1989 Application for Amend to License DPR-34,to Document Design Features for Defueling Phase of Operation ML20247G7201989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Fire Protection Limiting Condition for Operation & Surveillance Requirements from Tech Specs ML20247L0771989-09-14014 September 1989 Application for Amend to License DPR-34,deleting Limiting Condition for Operation 4.1.2 Through 4.1.6 & Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Adding Reactivity Section ML20247J2231989-09-14014 September 1989 Application for Amend to License DPR-34,incorporating Tech Spec Upgrade Program Including Requirements for Fuel Handling Machine Operation & Fuel Storage at Facility ML20246J3091989-08-30030 August 1989 Amend 72 to License DPR-34,imposing Early Shutdown on Plant by Limiting Reactor Power to 2% of Full Power After 900630 ML20245J3671989-08-14014 August 1989 Amend 71 to License DPR-34,revising Provisions in Tech Specs Re Radiological Effluents ML20246K9841989-07-14014 July 1989 Application for Amend to License DPR-34,changing Tech Specs to Document Improvements to Battery Surveillance Procedures ML20246L0161989-07-14014 July 1989 Application for Amend to License DPR-34,rewording Basis for Limiting Condition for Operation 4.2.2 Re Operation of Plant Backup Bearing Water Sys from Requiring Automatic Operation to Permitting Either Automatic or Manual Operation ML20244B3671989-06-0909 June 1989 Application for Amend to License DPR-34,adding License Condition Re Early Shutdown of Plant ML20245C4991989-04-18018 April 1989 Amend 70 to License DPR-34,changing Amount of Radioactive Matl to Be Possessed for Analysis & Instrument Calibr ML20245B3181989-04-14014 April 1989 Application for Amend to License DPR-34,extending for 90 days,4 H Check of Radiation Monitors Having Only Local Alarms to Permit Repair of out-of-svc Monitors W/O Reverting to Grab Sample Mode ML20248D6461989-03-31031 March 1989 Amend 69 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20236A1351989-02-27027 February 1989 Amend 68 to License DPR-34,modifying Limiting Condition for Operation 4.4.1 & Surveillance Requirement 5.4.1 to Include Fixed High Temp Trip Setpoint for Steam Line Rupture & Detection Sys ML20205F9781988-10-24024 October 1988 Amend 65 to License DPR-34,amending Tech Specs Paragraph 2.D(3) to Require Compliance W/Amended Physical Security Plan & to Conform to 10CFR73.55 Requirements ML20155J6051988-10-14014 October 1988 Application for Amend to License DPR-34,revising Tech Specs SR 5.0 & SR 5.2.1 Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20155J6231988-10-14014 October 1988 Application for Amend to License DPR-34,revising Administrative Controls Section of Tech Specs ML20204E7931988-10-13013 October 1988 Application for Amend to License DPR-34,revising Tech Specs to Clarify Time Allowed to Ensure Proper Trip Setpoints for Linear Channel - High Neutron Flux Channels Following Power Reduction ML20155G1821988-09-23023 September 1988 Application for Amend to License DPR-34,changing Format for Info Re Possession of Radioactive Matls for Purposes of Sampler Analysis or Instrument Calibr ML20154J4561988-09-15015 September 1988 Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls ML20154J7931988-09-15015 September 1988 Amend 64 to License DPR-34,changing Tech Specs for Plant DC Power Sys & Allowing for Future Changes to Station Batteries ML20207E1561988-08-0505 August 1988 Application for Amend to License DPR-34 ML20207F2141988-08-0505 August 1988 Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2 ML20207F0061988-08-0505 August 1988 Amend 61 to License DPR-34,deleting Requirement to Monitor Temp of Dew Point Moisture Monitors in Section 4.4 ML20151A9921988-06-20020 June 1988 Amend 60 to License DPR-34,revising Certain Setpoints for Protective Sys to Allow for Instrumentation Error ML20151S2411988-04-20020 April 1988 Application for Amend to License DPR-34,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery & Associated Battery Charger Disconnected from Dc Bus 1997-05-05
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Text
. _ _ _ _ - _ _ _ _ _ _
BEFORE THE UNITED STATES N'JCLEAR REGULATORY COP)iISSION In the Matter of the Facility Operating License)
)
of )
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PUBLIC SERVICE COMPANY OF COLORADO )
Application for Amendment to the Facility Operating License License No. OPR-34 0F THE PUBLIC SERVICE COMPANY OF COLORADO FOR THE ,
FORT ST. VRAIN NUCLEAR GENERATING STATION ,
1 This application for Amendment to tha Facility Operating License, Licen e Ne, DPR-34, is submitted for NRC review and approval.
Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO By R. O. Williams, Jr.
Vice President Nuclear Operations l
KELLY, STANSFIELD & 0'DONNELL James K. Tarpey Public Service Company Building c Denver, Colorado 80202 t
Attorneys for Applicant r
8810140117 880923 PDR ADOCK 05000267 p PDC 1
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' 0 4 e
AIIACll#ENT I
SUMMARY
OF PROPOSED Cil ANGES
Summary of Proposed Changes Section Description License Information 1) Reformat entire License Information Section, including deletion of the ccver letter, the Notice of Issuance j and the B-50 Agreement. '
- 2) Make the portion of the License Information which covers radioactive rnaterial possession similar to more "
recently licensed plants, f
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8 e ATTACllMJiNT Z PROPOSED CIIANGES k
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6
Amendmsnt No.
Page 1 of 4 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION DOCKET NO. 50-267 FACILITY ODERATING LICENSE ,
i License No. DPR-34
- 1. The Atomic Energy Commission (the Commission) having found that:
A. The application for license filed by the Public Service Company of Colorado (the licensee) complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Connission's rules and regulations set forth in 10 CFR Chapter 1 and all required notifications to other agencies or bodies have been duly made, B. Construction of the Fort St. Vrain Nuclear Generating Station (the facility) has been substantially completed in conformity with Provisional Construction Permit No. CDPR-54 and the i application, as amended, the provisions of the Act, and the rules and regu%tions of the Commission; C. The facility will operate in confornity with the application, l as amended, the provisions of the Act, and the rules and i regulations of the Commission; ;
D. There is reasonable assurance: (1) that the activities i authorized by this operating license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in co'npliance with the rules and regulations of the Commission; i
E. The licensee is technically and financially qualified to engage in the activities authorized by this operating license l
. in accordance with the rules and regulations of the -
Commission; l
]
l F. The licensee has satisfied the applicable provisions of :
10 CFR Part 140, "Financial Protection Requirements and r Identity Agreements," of the Commission's regulations; f G. The issuance of this operating license will not be inimical f to the common defense and security or to the health and }
safety of the public; j i I i
i I 1 ,
i
Amendment No.
Page 2 of 4 H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of I Facility Operating License No. DPR-34 (subject to the conditions for protection of the environment set forth herein) is in accordance with 10 CFR P.rt 50, Appendix D, of the Cor. mission's regulations and all applicable requirements of said Appendix 0 have been satisfied; and I. The receipt, possession, and use of source, byproduct, and special nuclear material as authorized by this license will be in accordunce with the Commission's regulations in 10 CFR Parts 30, 4C, 70, and 73.
- 2. Facility Operating License No. DPR-34 is hereby issued to the
. Public Service Company of Colorado to read as follows:
A. This license applir, to tne Fort St. Vrain Nuclear Generating Station, a high temperature gas-cooled nuclear reactor and associated equipment (the facility) owned by the Public Service Company of Colorado. The facility is located near Platteville, in Weld County, Colorado, and is described in the "Final Safety Analysis Report" as supplemented and i amended (Amencments 15 through 29) and the Environmental Report as supplemented and amended (Supplements 1 through 3).
B. This license is subject, for the initial rise to power, to the conditions set forth in Specification LCO 4.9-1 of the Technica! Specifications attached hereto as Appe,'ix A, C. Subject to the conditions and requirement. incorporated herein, the Commission hereby licenses the Puulic Service Company of Colorado:
(1) Pursuant to Section 104b of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities,: to possess use, and operate the facility at the designated location near Platteville in Weld County, Colcrado, in accordance with the procedures and limitations set forth in this license; l (2) Pursuant to the Act and 10 CFR Parts 40 and 70, to l receive, possess and use at any time source and special I nuclear material as reactor fuel, in accordance with the I limitations for storage and amounts required for reactor i oper tion, as describec in the Final Safety Analysis l Report, as supplemented anc amended; j (3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to l r9Ceive, possess, and use at any time any byproouct, l SJurce and special nuclear material as sealed neutron i sources for reactor startup, sealed sources for reactor
] instrumentation and radiation monitoring equipment l calibration, and as fission detectors in amounts as
] required;
Amendment No.
Page 3 of 4 ,
l (4) Pursuant to '.ne Act and 10 CFR Parts 30, 40, and 70, to l receive, possess and use in amounts as required any l byproduct, source or special nuclear material without l restriction to enemical or physical form, for sample l analysis or instrument calibration or associated with l radioactive apparatus or components; and l (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of l the facility authorized herein.
O. This license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I: Part 20, Section 30.34 of Part 30, !
Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50, and the appropriate sections of Parts 70 and 73; is subject to all applicable provisions of the Act and to the :
rules, regulations, and orders of the Commission new or l hereafter in effect; and is subject to the additional !
conditions specified or incorporated below: ,
i (1) Maximum Power Lesel, ;
The licensee is authorized to operate the facility at steady state reacsor core power levels not in excess of 842 megawatts thermal.
(2) Technical Specifications 1
The Te'chnical Specifications contained in Appendices A l and B, as revised through Amendment No. , are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
(3) Physical krotection The licensee shall fully implement and maintain in effect all provisions of the following Commission-approved documents, including amendments and changes made pursuant to the authority of 10 CFR 50.54(p):
- a. "Fort St. Vrain Unit No. 1 Security Plan" New consolidated issue dated Sepsyber 13, 1979, as revised through Revision 10, dated May 26, :9S2 (submitted June 2, 1952). (This document is with-held from public disclosure pursuant to 10 CFR 73.21.)
Amendment No.
Pege 4 cf 4 l
- b. Fort St. Vrain Guard Training and Qualification Plan (Appendix B to the Security P l a r. ) , dated February 1982 as evised April 6, 1982. This Plan t shall be followed in acccrdance with !
10 CFR 73.55(b)(4) 60 days after approval by the '
Commission. All security personnel, as required in the above plans, shall be qualified within two years i of this approval. The licensee may make changes to i this plan withoat prior Commission approval if tha L changes do not decrease the safeguards effectiveness I of the plan. The licensee shall maintain records of I and submit reports concerning such changes in the same manner as required for changes made to the Safeguards Coatingency Plan pursuant to r 10 CFR 50.54(p). (This document is withheld from l public disclosure pursuant to 10 CFR 73.21.) l
- c. Fort St. Vrain Safeguards Contingency Plan I (Appendiz C to the Security plan) dated April 6, 1982, submitted pursuant to 10 CFR 73.40. ,
The Contingency Plan shall be fully implemented, in accordance with 20 CFR 73.40(b). (This document is '
withheld from public disclosure pursuant to !
10 CFR 73.21.)
- d. Chapter 9, Fort St. Vrain Unit 1 Security Plan dated i June 10,1982 (suemitted June 11, 1992 revised tc ensure compliance with 10 CFR 73.45). (This chapter is classified CON F10ENTI Ai., National Security ,
Information.)
E. This license is subject to all Federal, State, and local standards imposed pursuant to the requirements of the Federal Water Pollution Control Act of 1972.
- 3. This license 'c effective as of tne date of issuance and shall expire at midnight, Septeeber 17, 2008.
FOR THE ATOMIC ENERGY COMMISS10N "0RIGINAL $1GNED BY:"
A. Giarbusso, Deputy Directsr for
- Reactor Projects 01 rectorate of Licensing 1
Attachrents:
1 Appendices A and E - Technical Specifications Cate of Issuance: Decerber 21, 1973 1
c
ATTACRMENI_1 SIGNIFICANT HAZARDS CONSIDERATION
4 . , ,, , .;
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T SIGNIFICANT HAZARDS CONSIDERATION 4 :
5 Description of Amendment Request: j This amendaent request is prompted by the need to have a 500 curie source of Costum 137 on site to perform calibration of high range detection instrumentation. Amendment 41 to the Fort St. Vrain :
Technical Specifications directed Public Service Company of Colorado I to, at a future time, replace the listing of specific isotopes with a statement similar to that now requested in 2.c.(4). The current Radiological Control Program maintains adequste control of the use and stnrage of calibration sources. '
- PSC is also proposing to delete the cover letter, the Notice of l l Issuance, and the B-50 Agreement. These deleted pages contain no }
license requirements which are not maintained in the License itself. :
This will serve to place the Fort St. Vrain License in a format more i i similar to the recently issued Licenses.
Basis for No Sionificant Hazards Determination:
The proposed change does not involve a significant hazards !
consideration because operation of FSV in accordance with this change !
would not: i r
(1) involve a significant increase in the probability or consequences f of an accioent previously evaluated. The use of sources for ;
calibration purposes does not effect the design or function of i any plant system / component. The updating of this license l condition to not specify individual isotopes will allow more i flexibility, and is being done based on an NRC recommendation.
(2) create the possibility of a new or different kind of accident J from any accident previously avaluated. Tne calibration of i detection instrumentation does not create the possibility of any [
accicent different from those already analyzed. Non-specific [-
designation of the calibration sources will not create any new failure modes, I
\
(3) involve a significant recuction in a margin of safety. There is ;
no margin of safety associated with calibration source strength. [
Further. reformatting the license coes not alter the requirements f expressett in the License, j
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