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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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o UNITED STATES
!" s o NUCLEAR REGULATORY COMMISSION
( n$ WASHINGTON, D. C. 20555
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l PUBLIC SERVICE COMPANY OF COLORADO DOCKET NO. 50-267 l i FORT ST. VRAIN NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No. DPR-34
- 1. The Nuclear Regulatory Commission (the Commission) has found that:
A. The application for amendment by Public Service Company of Colorado (the licensee) dated January 15, 1987 as supplemented June 24, 1987, complies with the standards and requirements of i the Atomic Energy Act of 1954, as amended (the Act), and the l Commission's rules and regulations set forth in 10 CFR Chapter I; l B. The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common 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 Commission's regulations and all applicable requirements have been satisfied.
8707110095 870629 PDR ADOCK 05000267 P PDR i
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l 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 j The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 55, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. This license amendment is effective when the Commission approves operation of facility at power levels higher than the 35 percent power currently authorized. The Commission expects that authorization of FSV to operate at power levels up to 82 percent of full power will follow the issuance of this amendment shortly.
FOR THE NUCLEAR REGULATORY COMMISSION i l
OdM &
Jose A. Calvo, Director
{
Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance: June 29, 1987
ATTACHMENT TO LICENSE AMENDMENT NO. 55 TO FACILITY OPERATING L5 CENSE NO. OPR-34 -
DOCKET NO. 50-267-l Replace the following page of the Appendix A Technical Specifications with the attached page as indicated. The revised page is identified by amendment number and contains a vertical line indicating the area of change. j 1
Remove Insert l
4.3-1 4.3-1 '
5.3-19 5.3-19 5.3-20 5.3-20 j i
i i
I h
Fort SR. Vrain Technical Specificatices Amend: .ent , 55 Page 4.3 1 1
I i
4.3 $ECONDARY REACTCR l00LANT $YSTEM
- LlWI**NG *0ND** ION $ CCR OPER.ATION arolicability l
Applies to the minimum configuration and characteristics of the I
secondary (steam) reactor coolant system, inciscing the steam 1
i generators and turbine plant. f l ]
l Objective To ensure the capability of this system to cool the core and prevent a safety limit from being exceeded by defining the minimum operable eculpment and characteristics of the secondary reactor coolant system.
Specification t.C0 4.3.1 - Steam Generators, Limitiro Conditions for Operatton The reactor small not be crerated at power v n'ess both t*e rereater section are tre economizer-evaporator-s.:erneater-(EES) l section of both steam generators are ope'able for e removal of decay heat.
I The EES sections shall be capable of receiving water f em both
! t*e energency concensate heater and the emergeecy feec= ster )
l *eacer. The reheater sections shall te capable of *eceiving
=ater f rom the emergeecy condensate heacer.
I Basis for (C0 4.3.1 l The stone gecerators provide the means for shutdown heat removal l from the primary coolant. The EE5 section of one steam l g e r.e ra to r is capable of fulfilliag this purpose for $4fe i Shutdown Cooling (refer to FSAR 5ections 10.3.9 and 14.4.2.2),
j as well as providing cooling for other abnormal events. The i reteater sections are capable of providing cooling for other
[ abnormal events, but are not relied upon to provide Safe i Shutcown Coo 11rg. The reheater section can be supplied water l from the emergency concer. sate header and the EES section can be i supplied water from either the emergency concensate heacer or j the teergency fete =4ter rescer.
l l
J Fort St. Vrain TechnicalSpegfiCations Arnendment
- Page 5.3 19 of one (or more) safety valve (s) of shilar type sad operating cencitions several times c.rieg t-e iaterval j additional conficence in safety valve i will provide reliability and adequate overpressure protection, I
5 specification 52 5.3.10 - secondary Ceclant System Instrumentation Surveillance The seconcary coolant rebeat steam instrumentation used a) for control and indication of emergeecy concensate flow to the repeaters and reheater backpressure, l i !
I b) to autocratically o;Ln the reheater cischarge by; ass on high pressure, and c) to monitor reFester discharge byoast te :erstyre, and j reaester inlet temperature, shall be functionally tested and calibratec aenwally, or at the cent scheduled plant shutdown if such surveillance I
was not performed during the previous year.
$R 5.3.10 sna11 be implemente cer 151 Criterion B.
_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _________.m..__._______ . _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ . _ _ _ . ___ _ _ ___ _ _ . _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _
l r,
Fort St. Vrain TechnicalSpegficatiers Arnendrr.ent d Page 5.3-20 Basis fe speci<tcation sa 51 :3 I*e freQwency specified for surveillance o' tte aDove
- strumentation will assure that they perform their espected automatic actions, and that the operator will be l
p ovided with accurste information which he can use to i I avoid abnormal eouipment eseration.
5: edification 5.3.11 - Steam Generator Bimetattic Welds 5,rveillance Se accessible portions of steam generator b{ metallic welds shall be volumetrically examined for indication $ of 5,bsurface defects as follows; a) The main steam ring header collector to main steam piping wele for ore steam gererator mocu'e in each loop at five ca'eacar year intervals, b) The main steam rieg header collector to collector drain piping weld for one steam generator module in each loop at five caleadar year intervals.
- ) The same two steam gererator mocules initta'ly selectec srall be r:-enamined at each interval, d) The bimetallic weles described in a) and b) shall also be inspected for two other steam generator modules in each loop during the inttial examination,
% $ 8 l