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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
[Table view] |
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" "" BEFORE THE L UNITED STATES NUCLEAR REGULATORY COMMISSION t
In the Matter of the Facility Operating' License)
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PUBLIC SERVICE COMPANY OF COLORADO )
Application for Amendment to Appendix A of Facility Operating License License No. DPR-34 0F THE PUBLIC SERVICE COMPANY OF COLORADO FOR THE FORT ST. VRAIN NUCLEAR GENERATING STATION This application for Amendment to Appendix A of Facility. Operating License, License No. DPR-34, is submitted for NRC review and approval.
Respectfully submitted, PUBLIC SERVICE COMPANY OF COLORADO By A. Clegg Crawford Vice President Nuclear Operations KELLY, STANSFIELD & 0'DONNELL James K. Tarpey Mark A. Davidson Public Service Company Building Denver, Colorado 80202 Attorneys for Applicant gg92gg(( h, ,gf P
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ATTACHMENT 1 TO P-89341
SUMMARY
OF PROPOSED CHANGES l
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SUMMARY
OF PROPOSED CHANGES LCO's 4.1.2 through 4.1.6, SR's 5.1.1, 5.1.2, 5.1.3, and 5.1.5 were superseded by the Interim Technical Specifications, by which PSC currently operates. This proposed amendment deletes the above listed LCO's and SR's, and adds a new Reactivity Control Section which supersedes the Interim Technical Specifications. The Reactivity Control Section is derived from the Technical Specification Upgrade Program (TSUP) as evaluated in Reference (2). Definitions Section 2.0, and Administrative Controls Section AC 7.1 are also revised to accommodate and reflect tho Technical Specifications, as amended.
Where applicable, specific relationships between current Technical Specifications / Interim Specifications, TSUP, and this submittal will be identified for clarity. Other supporting changes will be identified and summarized as applicable.
Specification Description of Change 2.3.b CHANNEL FUNCTIONAL TEST is added to the definition title. The definition remains unchanged.
2.18 Surveillance Interval is revised to delete the restriction associated with the termination of surveillance to those having an interval of one month or less.
2.23 CALCULATED BULK CORE TEMPERATURE is revised to reference the explanation in LC0 4.0.4.
2.24 Minor editorial changes are made to the CORE AVERAGE INLET TEMPERATURE definition, adopting the TSUP definition.
2.25 through Definitions are added from the TSUP 2.31 definitions section.
2.27 This definition is different from the TSUP in that the reactor power was changed to THERMAL POWER.
Section 4.1 Reactor Core and Reactivity Control Section LCO's 4.1.2, 4.1.3, 4.1.4, 4.1.5, and 4.1.6 are superseded by proposed specifications in the new Reactivity Control Section. The core reload design requirements have been deleted since there will be no more core reloads. See the later discussion for the proposed Reactivity Control Section.
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SUMMARY
OF PROPOSED CHANGES 3
- Specification Description of Change Section 5.1 Reactor Core and Reactivity Control SR's 5.1.1, 5.1.2,' 5.1.3, and 5.1.5 are superseded by proposed specifications in the new Reactivity Control Section. See the later discussion for the l
proposed Reactivity Control Section.
f SR 5.1.4 is revised to reference LC0 3.1.4 versus LCO 4.1.2.
AC 7.1.3 AC 7.1.3.8.b.1 is revised to reference new specification 3/4.1.5.
The new Reactivity Control Section includes Definitions Section 1.0, Applicability Specifications 3/4.0, and Reactivity Control Specifications which supersede other specifications as described below.
Section 1.0 The Definitions Section contains a description and table for operational modes as used in the Reactivity Control ' Specifications. -This definition is derived from the TSUP Definition 1.23 and Table 1.1.
- Section 3/4.0 The Applicability Specifications for LCO's and Surveillance in the Reactivity Control Section are mostly taken from the TSUP. Certain '
Specifications refer to current Technical i
Specifications, as applicable, instead of restating a similar Specification from the TSUP.
Reactivity Applicability LCO 3.0.1 through 3.0.4 are a duplication of the same TSUP Specifications.
LCO 3.0.5 refers to current LC0 4.0.4 for CALCULATED BULK CORE TEMPERATURE.
Reactivity Applicability SR's 4.0.1, 4.0.3, and 4.0.4 are a duplication of the same TSUP Specifications. SR 4.0.2 refers to Definition 2.18 for SURVEILLANCE INTERVAL adjustments.
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SUMMARY
OF PROPOSED CHANGES Specification Description of Change 3/4.0 (Cont.) The Bases for LCO's 3.0.1 through 3.0.4 are a duplication of the TSUP Bases, except the example for TSUP Specification 3.7.3 is deleted from the LCO 3.0.3 Basis. The Basis for- LCO 3.0.5 essentially refers to LCO 4.0.4.
The Bases for SR's 4.0.1 and 4.0.4 are- a duplication of the TSUP Bases. The Basis for SR 4.0.2 incorporates the Standard Technical Specification words as identified in Generic Letter 89-14. The Basis for SR 4.0.3 is a duplicate of the TSUP Basis except for editorializing the reference to SR 4.0.2.
3/4.1.1- New Reactivity Control Section, " Control Rod Pair Operability Specification," replaces Interim Specification 3/4.1.1 and is derived from TSUP Specification 3/4.1.1.
Differences between TSUP Specification 3/4.1.1 and the Reactivity Control Specification include:
reformatting, minor editorial changes such as clarifying that immediately is within 10 minutes, SR 4.1.1.a and d were incorporated into one Specification as SR 4.1.1.C, and references were updated.
3/4.1.2 New Reactivity Control Section, " Control Rod Pair Position Indication Systems-Operating," replaces Interim Specification 3/4.1.2 and is derived from TSUP Specification 3/4.1.2.1.
Differences between TSUP Specification 3/4.1.2.1 and the Reactivity Control Specification include reformatting, minor editorial changes, reference to LCO 3.1.5 versus 3.1.4.1, and references were updated.
3/4.1.3 New Reactivity Control Section, " Control Rod Pair Position Indication Systems-Shutdown," replaces Interim Specification 3/4.1.3 and is derived from TSUP Specification 3/4.1.2.2.
4
SUMMARY
OF PROPOSED CHANGES Specification Description of Change 3/4.1.3 (Cont.)' Differences between TSUP Specification 3/4.1.2.2 and the Reactivity Control Specification include reformatting, minor editorial changes, updating references, and the addition of "in fueled regions" for clarification in rod pair movement discussions. Refueling Surveillance intervals are changed to eighteen month periodicities, and the word " refueling" was deleted from 4.1.3.c.
3/4.1.4 New Reactivity Control Section, " Shutdown Margin,"
replaces Interim Specification 3/4.1.4 and is derived from TSUP Specification 3/4.1.3.
Differences between TSUP Specification 3/4.1.3 and the Reactivity . Control Specification include reformatting , the addition of "in fueled regions" for clarification in rod- pair movement discussions, and references were updated. The stipulation is also added that the Shutdown Margin shall be assessed prior to the removal of the control rod pair in a region to be refueled or repaired, only until all control rod pairs can be withdrawn without resulting in reactor criticality.
3/4.1.5 New Reactivity Control Section, " Control Rod Pair Position and Worth Requirements-Operating,"
replaces Interim Specification 3/4.1.5 and is derived from TSUP Specification 3/4.1.4.1.
Differences between TSUP Specification 3/4.1.4 and the Reactivity Control Specification include reformatting and editorial corrections, deletion of the reference to Special Test Exceptions l Specification 3.10.1, and references were updated.
3/4.1.6 New Reactivity Control Section, " Control Rod Pair Position Requirements-Shutdown," replaces Interim Specification 3/4.1.6 and is derived from TSUP
- Specification 3/4.1.4.2.
l I - - - - - - - - -- - - - - - - - - - - - - - - - - - - - - - - - - - _ _
SUMMARY
OF PROPOSED CHANGES Specification Description of Change 3/4.1.6 (Cont.) Differences between TSUP LCO 3.1.4.2 and the Reactivity Control Specification include reformatting, the addition of "in fueled regions"
'for clarification- in rod pair movement discussions, references were updated, and minor editorial corrections. The stipulation is also added that Specification 3/4.1.6 is applicable during Shutdown and Refueling, only until all control rod pairs can be withdrawn without
- resulting in reactor criticality. A revision was made to SR 4.1.6.D.1 for technical clarification.
Additional description is added to the Basis in regards to making all fully inserted ~ control rod pairs incapable of being withdrawn.
3/4.1.7 New Reactivity Control Section, " Reactivity Change With Temperature," replaces Interim Specification 3/4.1.7 and is derived from TSUP Specification 3/4.1.5. Reformatting changes only were made to the TSUP Specification.
3/4.1.8 New Reactivity Control Section, " Reserve Shutdown System-Operating," replaces Interim Specification 3/4.1.8 and is derived from TSUP Specification 3/4.1.6.1 Differences between TSUP LCO 3.1.6.1 and the Reactivity Control Specif.ication include reformatting, minor editorial changes, and updating references. The Basis is divided between the Reserve Shutdown System Operating and Shutdown Specifications, and edited accordingly.
3/4.1.9 New Reactivity Control Section, " Reserve Shutdown System-Shutdown," replaces Interim Specification 3/4.1.9 and is derived from TSUP Specification 3/4.1.6.2.
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SUMMARY
OF PROPOSED CHANGES Specification Description of Change 3/4.1.9 (Cont.) Differences. between TSUP LCO 3.1.6.2 and' the Reactivity Control Specification include reformatting, minor editorial changes, the addition of "from fueled ' regions" for clarification in rod pair withdrawal discussions, and updating references. Refueling Surveillance intervals are changed to eighteen months. The Basis is divided between Reserve Shutdown System Operating .and Shutdown Specifications, and edited accordingly.
An exception to the applicability of Specification 3/4.1.9 was added to identify that this specification does not apply if k(eff) s 0.95 with'all control rod pairs withdrawn.
NOTE: The numbering system for this proposed Reactivity Control Section is similar to that of the TSUP and the Interim Technical Specifications. The number
'3' signifies an LCO and a '4' is an SR. For example, 3/4.1.9 is the Specification entitled
' Reserve Shutdown System - Shutdown', 3.1.9 is the LCO, and 4.1.9 is the SR. This numbering scheme applies only to the Reactivity Control Section of the Technical Specifications. The rest of the Specifications will remain numbered as before; all LCO's are indicated with the number'4', and the SR's are numbered with a '5'.
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