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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
[Table view] |
Text
,
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+ IS UNITED STATES
- O i NUCLEAR REGULATORY COMMISSION
'j W ASHING TON, D. C. 20555
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PUBLIC SERVICE COMPANY OF COLORADO p0CKETNO.50-267 FORT ST. VRAIN NUCLEAR GENERATING STATION AltENDMENT TO FACILITY OPERATING LICENSE Amendment No. 69 License No. OPR-34
- 1. The Nuclear Regulatory Comissinn (the Comission) has found that:
A. The application for amendtnent by Public Service Company of Colorado (the licensee) dated December 23, 1986 as supplemented December 17, '
.. 1987, complies with the standards and re Energy Act of 1954, as amended (the , and Act)quirements the Comission's of the Atemic 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 Comission; C. There is reasonable assurance: (1) 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 cerducted in compliance with the Comission's regulations; D. The issuance of this license amendment will rot 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.
8004190090 000407 PDR ADOCK 05000P67 P ppa
- 2
- 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.0.(2) of Facility Operating License No. OPR-34 is hereby amended to read as follows:
(2) Technical Specifications The Technical Specifications centained in Appendices A and B, as revised through Amendment No,59, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
- 3. The license amerdmant is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
=
d , d/N Jose A. Calvo, Director <
Project Directorate - IV Division of Reactor Projects - III, l IV, Y and Special Projects l
j Office of Nuclear Reactor Regulation l
Attachment:
l Changes to the Technical l
Specifications Date of Issuance: April 7,1988 8 6 F
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'4 e ATTACHP.ENT TO LICENSE AffENCPENT NO. 59 FACILITY OPEPATING 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 ar.endment rumber and contain vertical lines indicating the areas of change.
Pemove Insert
4.3-8 4.3-8 4.3-9 to -
4.3-16 5.3-9 5.3-9 5.3.10 5.3-10 ,
5.3-11 5.3-11 5.3-15 - 5.3-15 e
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Fort _St. Vrain #1 Technical Specifications ,
Amendment No. /7,51 '
Page 4.3-7 Specification LC0 4.3.10 - Shock Suppressors ($nubbers) -
1.imitino Condition for Operation a) The reactor shall not be operated at power unless all l
Shock suppressors (snubbers) supporting Class I piping 1
systems are operable except as noted in b) through d) of this LCO.
l b) With one or more snubbers removed from service in a Class I system or subsystem, within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> replace ,
i or restore the snupber(s) to operable status. If one l
or more snubber (s) is found inoperable, within 72 e
I huurs replace or restore the inoperable snubber (s) and perform an engineering evaluation per Specification $R 5.3.8.c) on the supported component or declarm the supported system inoperable &Ld follow the appropriate action staterrent for that system.
l i
c) If the requirements of a) and b) of this LCO cannot be ,
met, an orderly shutdown shall be initiated and the f
reactor shall be in a low power condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. ,
4 d) If a shock suppressor is determined to be inoperable while the reactor is in the shutdown or refueling mode, the suppressee shall be made operable or replaced prior to reactor operation at power.
f l i i i
i I
t ___
,'~ Fort St. Vrain #1 Technical Specifications Amendment No. # ,59 Page 4.3-8 P
l l
Basis for Specification LC0 4.3.10
$ hock suppressors (snubbers) are designed to prevent unrestrained pipe motion under dynamic loads, as might occur during an earthquake, while allowing normal thermal motion during startup and shutdown. The consequence of an inoperable snubbec is an increase in the probability of structural damage to piping resulting from the dynande loads produced by a seismic event. It is therefore necessary that all snubbers required to protect the e Class I systems, subsystems, or componests be operable during reactor power operation.
Because snubber protection is required only during relatively low probability events, a period of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> is allowed for repair or replacement. In case a shutdown is required, the allowance of 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to reach a low power condition will pe rmit an orderly power reduction consistent with standard operating procedures. 31rce reactor operation at power should not be conducted with defective safety-relsted equipment, reactor power
- operation is prohibited with inoperable snubbers, except as Jteted above.
l
Fort St. Vrain #1 Technical Specifications Amendment No. 47,59 Page 5.3-9 activity level decreases to less than 10% of the limit of LCO 4.3.8, at which time weekly sampling may be resumed.
Basis for Specification $R 5.3.7 The specification surveillance interval is adequate to monitor the activity of the secondary coolant.
Specification SR $.3.8 - Shock Suppressors ($nubbers)
Surveillance ,
The following surve'lliance requirements apply to all Class I piping system shock suppressors (snubbers): '
a) Visual Inspections The first in-service visual inspection of snubbers shall be performed within six months from issuance of l this Technical $pecification (Amenoment H ). For the purpose of entering the schedule described in this section, it shall be assumed that the factitty had been on a six-month inspection interval. i
F
Fort St. Vrain #1 Technical Specifications Amendment No. A7, 59 Page 5.3-10 4
The first in-service visual inspection of snubbers l shall include all Class ! piping systes snubbers. If less than two snubbers are found inoperable during the first in-service visual inspection, the second in-service visual inspection shall be performed 12 months plus or minus 25% from the date of the first inspection. Otherwise, subsequent visual inspections shall be performed in accordance with the following schedule:
period Inspection period' 0 18 Months plus or minus 254 1 12 Months plus or minus 25%
2 6 Months plus or minus 25%
3, 4 124 Days plus or minus 25%
5,6,7 62 Days plus or minus 25%
8 or more 31 Days plus or minus 25%
'The inspection interval shall not be lengthened more than one step at a time, b) Visual inspection Acceptance Criteria Visual inspections shall verify (1) that there are no l
visible indications of damage or impaired operability, j (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snubber movement can be manually induced without disconnecting the snubber, that the snubber has j freedom of movement and is not seized. Snubbers which appear inoperable as a result of visual l
l l
, Fort St. Vrain el Technical Specific Amendment No M . DV gions Page 5.3-11 Inspections may be determined operable for the purpose of establishing the next visual inspection interval, providing that (1) the cause of .the rejection is clearly estabitshed and remedied for that particular snubber 49d for other snubbers that may be generically susceptible, and (2) the affected snubber is functionally tested in the as-found condition and l determined operable per Sections 5.3.8.d) and 5.3.8.e). However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be determined inoperable and cannot be determined OPERA 8LE via functional testing for the purpose of establishing the next visual inspection interval. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.
c) Functional Tests ,
At least once' per 18 months (not to exceed 221/2 months),a representative sample of each type of '
Snubber shall be tested using one of the following sample plans: The sample plan (s) shall be selected prior to the test period and cannot be changed during the test period. The NRC Regional Administrator shall be notified in writing of the sample plan (s) selected for each type of snubber prior to the test period or the sample plan (s) used in the prior test period shall be implemented:
- 1) At least 10% of the total of the type of snubber shall be functionally tested either in place or in e a bench test. For each snubber of that type that does not meet the functional test acceptance critsria of Specification $R 5.3.8.d) or SR 5.3.8.e), an additional 10% of that type of F
Fort St. Vrain #1 Technical Specific Amendment No. 47. 3 $tions
, Page 5.3-15 f) Enemetten From Visual Inspection or Functional Tests Permanent or other exemptions from the surveillance program for individual snubbers may be granted by the l Commission if a justifiable basis for 9xemption is l presented.
I g) neeord x...ino Record keeping shall consist of e
- 1) A historical record for each snubber shall be maintained. <
- 2) Concurrent with the first in-service visual inspection and at least once per refueling cycle thereafter, the historical recards for each l snubber shall be reviewed to deteen.ine any trends that may adversely affect service life.
- 3) The maximum expected service life for the various seals, seal materials, and applications shall be
! determined and established based on engineering information and the seals shall be replaced so that the maximum espected service Itfe will not be I *
! exceeded during a period when the snubber is required to be OPERABLE. This monitoring progras
.. shall be fully implemented within 22 1/2 months l
from the issuance of this Technical Specification (Amendment 39).
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