Application to Amend Tech Specs to Change Limiting Conditions of Core Thermal Power & Helium Flow Rate & Amount of Fuel Oil Required to Maintain Power Operated Relief Valve Cooling in Loss of Forced Circulation SituationsML19207C227 |
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Fort Saint Vrain |
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Issue date: |
08/29/1979 |
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From: |
Millen C PUBLIC SERVICE CO. OF COLORADO |
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To: |
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Shared Package |
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ML19207C223 |
List: |
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References |
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NUDOCS 7909100508 |
Download: ML19207C227 (14) |
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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20036A8241993-05-0707 May 1993 Proposed TS 4.3 Re Prestressed Concrete Reactor Vessel Water Leakage Protection ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20006B7921990-01-25025 January 1990 Proposed Tech Specs Re Administrative Title Changes to Section 7.1 ML19332F3561989-12-0404 December 1989 Proposed Tech Specs Re Limiting Condition for Operations 4.7.3, Fuel Storage Wells & 4.7.5, Instrumentation ML19332E8901989-12-0404 December 1989 Proposed Tech Specs Re Reactivity Control & Control Rod Pair Position Requirements During Shutdown ML19332C8151989-11-21021 November 1989 Proposed Tech Specs Revising Items 2.D.(1) & 2.D.(4) Re Max Power Level & Early Shutdown,Respectively ML19324B6961989-10-30030 October 1989 Proposed Tech Specs Re Reactor Core & Reactivity Control ML19351A3271989-10-13013 October 1989 Proposed Tech Specs 6.1 Re Defueling Phase Document Design Features ML19327B1321989-10-13013 October 1989 Proposed Tech Specs,Reflecting Deleted Limiting Conditions of Operations 4.1.2 Through 4.1.6,deleted Surveillance Requirements 5.1.1,5.1.2,5.1.3 & 5.1.5 & Newly Added Reactivity Control Section ML20248G4731989-10-0101 October 1989 Proposed Tech Specs Re End of Operations ML20248G4461989-09-30030 September 1989 Proposed Tech Specs Re Chlorine Detection & Alarm Sys & Control Room Emergency Ventilation Sys ML20247J2371989-09-14014 September 1989 Proposed Tech Specs Re Fuel Handling & Storage ML20247L1721989-09-14014 September 1989 Proposed Tech Specs Re Reactivity Control ML20247G7341989-09-14014 September 1989 Proposed Tech Specs Deleting Fire Protection Limiting Condition of Operation & Surveillance Requirements from Tech Specs ML20247G7811989-09-14014 September 1989 Proposed Tech Specs,Documenting Design Features for Defueling Phase of Operation ML20246L0231989-07-14014 July 1989 Proposed Tech Specs,Rewording Basis for Limiting Condition for Operation 4.2.2 Re Operable Circulator ML20246K9921989-07-14014 July 1989 Proposed Tech Specs Documenting Improvements to Battery Surveillance Procedures ML20244B3771989-06-0909 June 1989 Proposed Tech Specs Re Early Shutdown of Plant ML20245B3211989-04-14014 April 1989 Proposed Tech Specs Re Radiation Monitors & Noble Gas Monitors ML20155J6281988-10-14014 October 1988 Proposed Tech Specs Concerning Administrative Controls ML20155J6111988-10-14014 October 1988 Proposed Tech Specs Re Pcrv & Pcrv Penetration Overpressure Protection Surveillance ML20204E8171988-10-13013 October 1988 Proposed Tech Specs Re Linear channel-high Neutron Flux Trip Setpoints ML20207E1591988-08-0505 August 1988 Proposed Tech Specs Re Auxiliary Electric Sys Involving Proposed Change of Dc Batteries ML20155J7181988-06-14014 June 1988 Revised Draft Tech Specs 3/4.6.5.2,deleting Charcoal Filter Test Exceptions After Painting W/Low Solvent paints,6.5.1.2 & 6.2.3.3,reflecting Recent Util Reorganization & 3/4.7.1.5 & 3/4.7.1.6,requiring One Operable Valve Per Loop ML20151R8191988-04-20020 April 1988 Proposed Tech Specs,Deleting 10CFR51.5(b)2 ML20151S2471988-04-20020 April 1988 Proposed Tech Spec Pages 4.6-4 & 4.6-8,allowing Up to 5 Consecutive Days to Perform Equalizing Charge W/Station Battery ML20148N2751988-03-29029 March 1988 Proposed Tech Specs,Deleting Requirement to Monitor Ambient Temp in Instrument Penetrations Housing Flow Sensors for Dewpoint Moisture Monitoring Sys ML20149M2901988-02-0808 February 1988 Proposed Tech Spec Re Plant Protective Sys Trip Setpoint & Operating Requirements ML20149N0391988-02-0505 February 1988 Proposed Tech Specs Re Changes to Administrative Controls to Reflect Organizational Changes in Util & NRC ML20238C3481987-12-23023 December 1987 Proposed re-drafted Tech Specs,Upgrading Sections Re safety- Related Cooling Sys.Related Info Encl ML20236C6361987-10-15015 October 1987 Proposed Tech Specs,Deleting Fire Protection Limiting Conditions for Operation & Surveillance Requirements ML20235W8611987-10-0101 October 1987 Proposed Tech Specs,Clarifying Actions on Inoperable Halogen or Particulate Monitors & Conditions Requiring Weekly Gamma Spectral Analysis on Inservice Gas Waste Tank ML20235B0091987-08-28028 August 1987 Proposed Tech Specs Re Trip Setpoints & Operating Requirements ML20216H7301987-06-25025 June 1987 Proposed Tech Specs,Adding Definition of Calculated Bulk Core Temp & Core Average Inlet Temp for Determination of Core Temp ML20210B7081987-04-23023 April 1987 Proposed Tech Specs Re Surveillance & Calibr Requirements of Plant Protective Sys Parameters ML20206P3931987-04-0808 April 1987 Proposed Tech Specs,Revising 3/4.1.7, Reactivity Change W/Temp to Be Consistent W/Increased Values for Calculated Reactivity Worth of Reserve Shutdown Sys,Per Rev 4 to FSAR, Section 3.5.3.3 ML20207P9911987-01-15015 January 1987 Proposed Tech Specs,Requiring Both evaporator-economizer Superheater Sections & Both Reheater Sections to Be Available During Operation at Power as Min Number of HXs ML20207D2421986-12-23023 December 1986 Proposed Tech Specs Deleting Snubber Tables & Correcting Typos 1996-02-22
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20148U0111997-06-17017 June 1997 Confirmatory Survey of Group E Effluent Discharge Pathway Areas Fsv Nuclear Station Platteville,Co ML20133D7661996-09-16016 September 1996 Confirmatory Survey Plan for Fsv Nuclear Station Decommissioning Project ML20129A4621996-09-11011 September 1996 Rev 0 to Fsv Decommissioning Project Final Survey Requirements for Liquid Effluent Pathway ML20100L3581996-02-22022 February 1996 Proposed Tech Specs,Submitting Corrected Version of Plant Decommissioning TS Updated to Reflect All Approved Amends ML20097C2601996-01-17017 January 1996 Confirmatory Survey Activities Plan for Fsv Nuclear Station PSC Platteville,Co ML20101F2091995-09-18018 September 1995 Issue 7 to DPP 5.4.2, Odcm ML20084B8801995-05-25025 May 1995 Rev 1 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20084B6881995-05-10010 May 1995 Issue 5 to Fire Protection Operability Requirements (Fpor) FPOR-7, Fire Extinguishers ML20082K2461995-04-14014 April 1995 Proposed Decommissioning Tech Specs Administrative Control 5.3.1,reflecting Organizational Changes That Impact Membership of Decommissioning Safety Review Committee ML20082T2151995-04-12012 April 1995 Issue 7 to Fire Protection Operability Requirements (Fpor) FPOR-12, Fire Detectors ML20082B9411995-03-17017 March 1995 Confirmatory Survey Plan for Repower Area,Fort St Vrain, Platteville,Co ML20082C0801995-03-16016 March 1995 Proposed Confirmatory Survey Plan for Repower Area,Fort St Vrain,Platteville,Co ML20082B9821995-03-15015 March 1995 Instrumentation Comparison Plan Between Orise & Fort St Vrain ML20086S2471995-02-0909 February 1995 Decommissioning Plan for Fort St Vrain Nuclear Generating Station ML20077C7171994-11-30030 November 1994 Issue 9 to FPOR-14, Fire Protection Operability Requirements ML20078C0641994-10-12012 October 1994 Revised Fire Protection Operability Requirements,Including Issue 21 to Depp Table of Contents,Issue 2 to FPOR-22 & Issue 3 to FPOR-23 ML20081J7951994-09-15015 September 1994 Issue 5 to DPP 5.4.2, Odcm ML20063M1551994-02-17017 February 1994 Rev 0 to Fsv Nuclear Station Decommissioning Project Final Survey Plan for Site Release ML20057A6151993-08-30030 August 1993 Issue 2 to FPOR-23, Fire Water Makeup Sys ML17291B3261993-05-18018 May 1993 Proposed TS Section 2.2 Re Activated Graphite Blocks,Section 2.4 Re Channel Calibr & SR 3.2.1 Re Verification of Reactor Bldg Pressure & SR 3.2.2 Re Verification of Pressure Drop Across Each HEPA Filter ML20036A8241993-05-0707 May 1993 Proposed TS 4.3 Re Prestressed Concrete Reactor Vessel Water Leakage Protection ML20118B2141992-09-25025 September 1992 Proposed Decommissioning Tech Specs Replacing Radiation Safety with Nuclear Safety, Revising Applicability Requirements for Specs Dealing W/Reactor Bldg Confinement Integrity & Clarifying Items Re Unreviewed Safety Questions ML20114D6871992-09-0101 September 1992 Tritium Leach Test on H-327 Graphite ML20096H1961992-05-19019 May 1992 Decommissioning TS Deleting Section 4.2.15 Re LCO 4.2.15 Covering Pcrv Cooling Water Sys Temps ML20095B0951992-04-14014 April 1992 Proposed Tech Specs Re Organization,Review & audit-administrative Controls ML20094L2831992-03-19019 March 1992 Proposed Tech Specs Re Controls & Limits Appropriate for Decommissioning ML20086C5301991-11-15015 November 1991 Proposed Tech Spec Limiting Condition for Operation 4.2.15 Re Pcrv Cooling Water Sys Temps ML20079M4261991-10-11011 October 1991 Revised Abnormal Operating Procedures,Reflecting Deletion of Issue 9 of EP Class ML20091D7631991-10-11011 October 1991 Proposed,Revised Limiting Condition for Operation 4.2.15 Re Prestressed Concrete Reactor Vessel Cooling Water Sys Temp ML20082L9311991-08-30030 August 1991 Proposed Tech Specs Re Decommissioning ML20082H8851991-08-16016 August 1991 Issue 2 to Abnormal Operating Procedure AOP-I-2, Chemical, Petroleum & Hazardous Waste Spill Response ML20091C4141991-08-0202 August 1991 Issue 58 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20024H3341991-05-10010 May 1991 Nonproprietary Rev 2 to FSV-P-SCP-100, Fort St Vrain Initial Radiological Site Characterization Program Program Description ML20072V5291991-04-12012 April 1991 Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization ML20070V6871991-03-20020 March 1991 Issue 55 to Abnormal Operating Procedure AOP-R, Loss of Access to Control Room ML20072S0521991-03-15015 March 1991 Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 9 to CMIP-11, Classification of Emergency for McGuire Nuclear Station & Rev 11 to CMIP-12, Classification of Emergency for Oconee Nuclear Station ML20066J1171991-02-15015 February 1991 Issue 56 to Intro Section of Abnormal Operating Procedure (Aop),Issue 58 of AOP-A,Issue 58 to AOP-B,Issue 56 of AOP D-1 & Issue 2 of RERP-TRANSPORTATION ML20066A3781990-12-21021 December 1990 Proposed Decommissioning Tech Specs Re Reactor Bldg Integrity,Reactor Bldg Ventilation Exhaust Sys,Radiation Monitoring Instrumentation & Pcrv Shielding Water Tritium Concentration ML20059L5891990-09-14014 September 1990 Proposed Tech Specs Changing Design Features Section 6.1 to Permit Removal of CRD & Orifice Assemblies from Core Regions Defueled in Support of Plant Closure Activities ML20058N1071990-08-10010 August 1990 Issue 56 to AOP-I, Discussion of Fire ML20042F3151990-04-26026 April 1990 Proposed Tech Specs Re Defueling ML20034C7851990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-EP Q, Steam Leak or Inadvertent Lifting of Steam Relief Valve ML20034C7781990-04-25025 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-2, Abnormal Radioactive Gas Release from Plant ML20034C7831990-04-19019 April 1990 Issue 56 to Abnormal Operating Procedure AOP-N, Loss of Instrument Bus ML20034C7761990-04-19019 April 1990 Issue 55 to Abnormal Operating Procedure AOP D-1, Single Circulator Trip ML20034C7771990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-1, Abnormal Radioactive Liquid Waste from Plant ML20034C7841990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-P, Loss of DC Bus ML20034C7801990-04-19019 April 1990 Issue 59 to Abnormal Operating Procedure AOP-K-1, Environ Disturbances - Earthquake ML20034C7821990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-L, Loss of Instrument Air Header ML20034C7791990-04-19019 April 1990 Issue 57 to Abnormal Operating Procedure AOP-H-3, High Activity in Plant 1997-06-17
[Table view] |
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i BllfEP2 Tif E lluITED STATES NUCL::AR PIGL"uATORY C072fISSIO:i In the !!atter of the Facility Oncrating License)
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PUliLIC SERVICE C01:PA'iY OF COLORADO
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Application for Anendmnt to Appendix A of Facility Operating License Licenae No. DP R-34
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OF THE PUdLIC SERVICE COMPA'iY OF COLORADO FOR TiiE "0RT ST. VRAIN iiUCLl:AR C10?ERATI?iG SYATIO!T This application for Anendaent to Appendix A of Facility Op eratin;; Licens e, Licenne :10 DP R-34, is aubnitted for :iRC reviev and approval.
Frapectfully submitted, PLILIC S ERVICE CO?DTTY OF COLOFX00 y
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C. K.
ac, Senior Vice President SFIELD & 0' DO:!'iELL
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- Donnel obert 9iorpson Public Servic, Conoony Building Denve r, Coloraco 02U2 Attorneys f o r Anplican t o.,,,q'*
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g6 STATE OF COLOPADO
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CITY AfD ColIITY OF D;NVER)
C. K.11111en, being first duly sworn, deposes and says;
'niat he is Senior Vice President of Operations of Public Service Company of Colorado, the Licensee herein; that he has read the foregoing Application for Amend: cut to Appendix A of Facility Operating License and knows the contents thereof, and that the staterents and natters set forth therein are true and correct to the beat of his knavledge, information and b elief.
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C. K. Stillen Subacribed and nuorn to before te this G
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this delay period can be allowed without compromising the integrity of the fuel. As a result of many transient analyses, the delay period has been con-servatively set at 100 seconds for transients resulting in a power-to-flow ratio above 2.5 but less than or equal to 15 and 60 seconds if the power-to-flow ratio is greater than 15.
The allowable time, af ter the delay time, for all transients which lead to a power-to-flow ratio in excess of 2.5 is set at 2 minutes which is also the allowable time for a power-to-flow ratio of 2.5 given by Figure 3.1-1.
The limitation of allowable operating time to a value of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> for all operations with a power-to-flow ratio above the curve of Figure 3.1-2 and below a value of 1.17 provides a conservative limit since this is the allowable time for a power-to-flow ratio of 1.17 given by Figure 3.1-1.
Limiting the continuous operating time in this range of power-to-flow ratios to a value of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> is additionally conservative.
The 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> continuous operating time limit must be included as a fraction of the 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> allowable time.
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ATTAG MENT 2 33013.1
- me Basis for Specification LCO 4.2.17 The ACM diesel generator provides power independently of the plant elec-trical distribution network to various valves, lighting, and pieces of equip-ment.
That equipment provides an alternate means of maintaining PCRV cooling during the Loss of Forced Circulation situation described in the Final Safety Analysis Report, Section 14.10.
The 10,000 gallons of fuel provides for 108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br /> operation of the gen-erator with full ACM load, which is adequate time for obtaining additional fuel from off site sources.
Reason for Change The information used to initially establish the time that 10,000 gallons of fuel oil would provide for full ACM load used a fuel consumption rate which was more conservative than that determined by actual test.
A fuel oil consump-tion test was performed which established that 10,000 gallons of fuel oil will provide for 41/2 days (108 hours0.00125 days <br />0.03 hours <br />1.785714e-4 weeks <br />4.1094e-5 months <br />) operation with full ACM load of 900 KW.
3.301bd