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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20141K9941997-05-0505 May 1997 Amend 89 to License DPR-34,designating All Elements of Approved Decommissioning Plan as License Termination Plan 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 ML20245C4991989-04-18018 April 1989 Amend 70 to License DPR-34,changing Amount of Radioactive Matl to Be Possessed for Analysis & Instrument Calibr 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 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 ML20154J4561988-09-15015 September 1988 Amend 63 to License DPR-34,changing Tech Spec Section 7 Re Administrative Controls 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 ML20207F2141988-08-0505 August 1988 Amend 62 to License DPR-34,deleting Ref in App B of Tech Specs to 10CFR51.5(b)2 ML20151A9921988-06-20020 June 1988 Amend 60 to License DPR-34,revising Certain Setpoints for Protective Sys to Allow for Instrumentation Error ML20148S5901988-04-0707 April 1988 Amend 59 to License DPR-34,deleting Tabular Listing of safety-related Snubbers from Tech Specs ML20236U5191987-11-23023 November 1987 Amend 57 to License DPR-34,revising Tech Specs to Ensure Sufficient Helium Coolant Flow to Prevent Overheating of Fuel While in Low Power or Shutdown Modes ML20235N6441987-07-13013 July 1987 Amend 56 to License DPR-34,changing Certain Administrative Controls Under Which Plant Operated,In Partial Response to 860722 & 1205 Applications.Tech Spec Pages Encl ML20235E5201987-06-29029 June 1987 Amend 55 to License DPR-34,revising Tech Spec to Require Both Sections of Both Steam Generators to Be Available for DHR in Power Operation ML20214M4401987-05-20020 May 1987 Amend 54 to License DPR-34,modifying Surveillance Requirements for Standby Diesel Generator ML20215J8201987-05-0505 May 1987 Amend 53 to License DPR-34,changing Tech Specs to Show Actual Location of Fire Hose Station TH12-G4 ML20206J8411987-04-0606 April 1987 Amend 52 to License DPR-34,increasing Circulator speed-high Steam Trip Setting Listed in Table 4.4-3 of Tech Specs ML20207S1951987-03-0909 March 1987 Amend 51 to License DPR-34,revising Portions of Section 5.2 Through 5.4 of Tech Specs.Sections Pertain to Phase II of Util Inservice Insp & Testing Program ML20212J3171987-02-26026 February 1987 Amend 50 to License DPR-34,changing Tech Specs Re Steam Line Rupture Detection/Isolation Sys ML20212A8971986-12-15015 December 1986 Amend 49 to License DPR-34,revising Tech Specs to Add Section 4.9.3 Re Xenon Stability Testing ML20214P6731986-11-25025 November 1986 Amend 48 to License DPR-34,adding Section 7.7 Concerning Formalized Fuel Surveillance Program to Tech Specs ML20206C6721986-06-12012 June 1986 Corrected Amend 47 to License DPR-34,modifying Tech Specs to Allow Replacement of Mechanical Snubbers W/Hydraulic Snubbers ML20141N5451986-03-0404 March 1986 Amend 47 to License DPR-34,changing Tech Specs to Allow Mechanical Snubbers to Be Replaced by Equivalent Hydraulic Snubbers ML20244A6521979-04-20020 April 1979 Amend 20 to License DPR-34 to Revise Tech Specs to Install Eight Test Fuel Elements Into Reactor Core at First Refueling & to Install Graphite Surveillance Specimens Into Five Bottom Transition Reflector Elements 1997-05-05
[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
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- UNITED STATES
[ g NUCLEAR REGULATORY COMMISSION
.- r. WASHING TON, D. C. 20555
- l
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PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 64 License No. OPR-34 -
- 1. The Nuclear Regulatory Comissior, (the Comission) has found that:
A. The application for amendirent by Public Service Company of Colorado (the licensee) dated April 20, 1988 as supplemented July 1 and August 5, 198E, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Convaission; C. There is reasonable r surance: (1)thattheactivitiesauthorized by this arrendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D. The issuance of this license amendment will not be inimical to the comon defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.
eso9230130 000'/15 7 DR ADdCK 0000
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.D.(2) of Facility Operating License No. DPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 64, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amendment is effective as of its date of issuance.
F FOR THE NUCLEAR REGULATORY COMMISSION
,&c G h.. !w Jose A. Calvo. Director Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects Office of Fuclear Reactor Regulation Attachraent:
Changes to the Technical Specifications Date of Issuance: September 15, 1988 l
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.c . , ,
. ATTACHMENT TO LICENSE AMENDMENT NO. 64 TO FACILITY OPERATING LICENSE NO. OPR-34 DOCKET NO. 50-267 Replace the following pages of the Appendix A Technical Specifications with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
R_woy Insert 4.6-3 4.6-3 4.6-5 4.6-5 4.6-6 4.6-6 t
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Fort St. Vrain #1
. Technical Specifications Amendment No.14, 64 Page 4.6-3 i operability of the other diesel-generator set is demonstrated innediately as in a) above and all essential buses are operable, e) The two station batteries and their associated D.C. buses and battery chargers are operable. One battery charger or battery may be l inoperable for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, unless disconnected to perform an l equalizing charge, provided conditions 1 through 4 below are satisfied.
- 1) The other station battery and its associated battery charger and both D.C. buses are operable.
l 2) 0.C. bus independence is maintained and the disconnect switch l for the PPS battery is open.
- 3) Both diesel-generators and their associated essential 480v buses are operable.
- 4) The PPS battery and battery charger / inverter are operable.
A battery and battery charger disconnected from a D.C. bus to perform an equalizing charge is considered inoperable, but may be disconnected for up to 5 consecutive days provided conditions 1) through 4) above are met.
One D.C. bus may be inoperable for 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> provided the following conditions are satisfied:
- 1) The station battery and the associated battery charger of the operable D.C. bus are operable.
- 2) Instrument power inverter supplied from the operable D.C. bus is operable.
- 3) Both diesel-generators and.their associated 480v essential buses are operable.
Fort St. Vrain #1
. Technical Specifications Amendment No.JA, 64
. Page 4.6-5 i
In the nonnal operating mode, the unit auxiliary transformer is in operation, reserve aeviliary transfomer is energized and the standby-generator sets are operable. (FSAR Section 8.2.3.3.)
The main turbine-generator can be used as a source of auxiliary power in the event that outfdde electrical power is lost.
In the event of loss of all outside power and a turbine-generator trip, the diesel-generator sets would come on automatically to provide the required energy necessary to safely shut down the plant. .
In the event of the loss of the Reserve Auxiliary Transformer when the main turbine-generator is out of service, links in the bus between the main turbine-generator and the main power transformer can be removed, allowing the main power transformer and unit auxiliary transformer to be returned to service.
The essential 480v power source is supplied from three separate buses,
- any two of which can supply adequate power to shut the plant down. Under accident conditions, if the normal supply of power to these three essential buses should fail, the diesel-generator sets would come on and energize them. Bus load shedding, breaker closing, and load sequencing on to the diesel-generator sets is handled automatically.
The station batteries supply power for the instrument power inverters, protective devices and equipment operational control. During nomal operation, D.C. power is supplied by A.C. to D.C. rectifiers, that is, battery chargers, which also keep the batteries fully charged. (FSAR Section 8.2.2.4.)
Fort St. Vrain #1 Technical Specifi tions Amendment No M .
Page 4.6-6 The backup sources of electric power for the non-interruptible A.C.
l Instrument Power Buses are provided from Instrument Power Transformers fed from the 480 VAC essential buses through the Inverter / Static l Transfer Switches. Interruptible Instrument Bus No. 3 receives its power from redundant instrument transformers which are supplied from the essential 480 volt switchgear. (FSARSection8.2.2.3.)
A redundant source of electric power for the D.C. instrument loads is available from bus tie breakers between the two D.C. buses which allows' l the backup battery charger to supply either one of the two buses while maintaining D.C. bus independence.
These backups and redundancies permit the temporary removal from service of an instrument power inverter, a battery, a D.C. bus or a l battery charger.
A diesel fuel storage capacity of 50,000 gallons is provided. A supply of 20,000 gallons of diesel fuel is adequate to provide for operation of the standby generators for at least seven days under required loading conditions. This allows adequate time to obtain additional fuel and to
. make provisions to restore the standby source of power into the station.
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