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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20217F9551999-10-14014 October 1999 Application for Amends to Licenses DPR-77 & DPR-79,proposing Change to TS SRs & Bases to Incorporate ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plant Intersections ML20217E4211999-10-12012 October 1999 TS Change 99-15 to Licenses DPR-77 & DPR-79,providing Unisolation of Containment Penetrations Under Administrative Controls ML20211K1521999-08-30030 August 1999 TS Change 99-10 to Licenses DPR-77 & DPR-79,providing Clarification to Current TS Requirements for Containment Isolation Valves ML20211M7261999-08-30030 August 1999 TS Change 99-08,for Amends to Licenses DPR-77 & DPR-79 to Provide Alternative to Requirement of Actually Measuring Response times.Marked-up & Revised TS Pages,Encl ML20209B7661999-06-30030 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,updating Current TS Requirements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196G4441999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Revise TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196F2121999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Change TS Allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20195E9661999-06-0707 June 1999 Application for Amend to License DPR-79,increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/ Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20206E1551999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 99-04, Auxiliary Feedwater Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20206E1341999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change Request 99-03, Main Control Room Emergency Ventilation Sys Verses Radiation Monitors. Change Adds LCOs 3.3.3.1 & 3.7.7 & NUREG-1431 Changes ML20204H3991999-03-19019 March 1999 TS Change 99-01 to Licenses DPR-77 & DPR-79,relocating TS Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D5941999-02-26026 February 1999 Application for Amend to Licenses DPR-77 & DPR-79,relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6251999-02-26026 February 1999 Application for Amends to Licenses DPR-77 & DPR-79,revising TS to Provide for Consistency When Exiting Action Statements Associated with EDG Sets ML20199K5841999-01-15015 January 1999 Application for Amends to Licenses DPR-77 & DPR-79,adding New Action Statement to TS 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Protection ML20206S0061999-01-15015 January 1999 TS Change 98-09 for Licenses DPR-77 & DPR-79,relocating TS 3.3.3.3, Seismic Instrumentation & Associated Bases from TS to Plant Technical Requirements Manual ML20195H6041998-11-16016 November 1998 Application for Amends to Licenses DPR-77 & DPR-79,revising EDG SRs by Adding Note to Allow SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Lockout Features ML20154H7201998-10-0808 October 1998 Supplemental Application for Amends to Licenses DPR-77 & DPR-79,changing TS to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1051998-08-27027 August 1998 Application for Amend to License DPR-79,revising TS to Provide for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F2981998-08-27027 August 1998 Revised Applications for Amends to Licenses DPR-77 & DPR-79, Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of Edg.Response to RAI Included in Encl ML20249C6321998-06-26026 June 1998 Application for Amends to Licenses DPR-77 & DPR-79,lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248E9841998-05-28028 May 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,replacing Direct Ref to Nuclear QA Plan in TS Section 6.3.1,facility Staff Qualification,W/Actual Requirements Stated in TVA-NQA-PLN89-A ML20217N3411998-04-30030 April 1998 Application for Amends to Licenses DPR-77 & DPR-79,modifying TS Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1511998-02-25025 February 1998 Application for Amends to Licenses DPR-77 & DPR-79 to Change TS for Units 1 & 2,revising EDG Surveillance Requirements ML20202J6601998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79, Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7101998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79,adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20202J7421998-02-13013 February 1998 TS Change 97-04 to Application for Amends to Licenses DPR-77 & DPR-79,relocating Snubber Requirements from Section 3.7.9 of TS to Plant Technical Requirements Manual ML20198T4211998-01-21021 January 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,revising Title for President,Tva Nuclear & Chief Nuclear Officer to Generic Title of Chief Nuclear Officer ML20199K4441997-11-21021 November 1997 Application for Amend to License DPR-55,adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3091997-09-17017 September 1997 TS Change 97-02 to Licenses DPR-77 & DPR-79,revising Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137C8271997-03-19019 March 1997 Revised TS Change 96-01 to Licenses DPR-77 & DPR-79,revising Appropriate Specifications,Surveillances & Bases to Allow for Conversion from Westinghouse Fuel to Framatome Cogema Fuel ML20136J0251997-03-13013 March 1997 Application for Amends to Licenses DPR-77 & DPR-79,revising Allowed Enrichment of Fuel in TS Section 5.6.1.2 for New Fuel Pit Storage Racks from 4.5 to 5.0 Weight % U-235 ML20129D2561996-10-18018 October 1996 Application for Amends to Licenses DPR-77 & DPR-79,removing Existing Footnotes That Limit Application of Apc for Plant SG Tubes to Cycle 8 Operation for Both Units ML20129G7111996-09-26026 September 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Fire Protection License Conditions & Relocation of Fire Protection Tech Spec ML20113G2421996-09-20020 September 1996 Application for Amends to Licenses DPR-77 & DPR-79, Clarifying Work Shift Durations for Overtime Limits ML20117J3341996-08-28028 August 1996 Application for Amends to Licenses DPR-77 & DPR-79, Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D0921996-08-22022 August 1996 Application for Amends to Licenses DPR-77 & 79 Changing Tss of Sqb Units 1 & 2 by Deleting Table 4.8-1, DG Reliability & Revising Sectio 3.8.1 to Allow a Once Per 18 Month 7 Day AOT for EDGs ML20117D3271996-08-21021 August 1996 TS Change 96-06 to Licenses DPR-77 & DPR-79,removing Surveillance Requirement 4.8.1.1.1.b to Verify Ability to Transfer Unit Power Supply from Unit Generator Supported Circuit to Preferred Power Circuit ML20117D2931996-08-21021 August 1996 TS Change 96-03 to Licenses DPR-77 & DPR-79,revising TS 3.7.1.3, Condensate Storage Tank, to Include New Mode of Applicability to Read Mode 4 When SG Relied Upon for Heat Removal ML20112H0361996-06-0707 June 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N6981996-04-0404 April 1996 TS Change 96-01 to Licenses DPR-77 & DPR-79,allowing Use of Nuclear Fuel Provided by Framatome Cogema Fuels (Fcf). Proprietary & Nonproprietary Versions of Fcf TR Supporting TS Change 96-01 Encl.Proprietary Version of TR Withheld ML20096B3671996-01-0404 January 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising TS Change 95-22,extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20095F0271995-12-12012 December 1995 Application for Amend to License DPR-79,consisting of TS Change 95-23 Revising TS SRs & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20095D5731995-12-0808 December 1995 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 95-20,extending Containment Spray & RHR Sys Nozzles Testing Period from 5 to 10 Yrs in Accordance W/Gl 93-05 ML20095D5431995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,consisting of TS Change 93-09,revising Setpoints & Time Delays for AFW loss-of-power & 6.9 Kv Shutdown Board loss-of-voltage & degraded-voltage Instrumentation ML20095D5811995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,revising TSs to Implement Recent Rule Change to 10CFR50,App J ML20092E0191995-09-11011 September 1995 Application for Amend to License DPR-79,consisting of TS Change Request 95-13,rev 1 Re Extension of Response Time Surveillance Requirements for Unit Two Cycle 7 ML20092E0351995-09-0808 September 1995 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 3/4.7.8 to Clarify Intent of Vacuum Relief Flow During TS Required Testing of Auxiliary Bldg Gas Treatment Sys ML20092E2741995-09-0707 September 1995 Revised TS Change 95-15 for Amend to License DPR-77,revising TS Surveillance Requirements & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20091K4241995-08-21021 August 1995 Proposed TS Change 95-21 to Licenses DPR-77 & DPR-79, Revising TS LCO 3.7.5.c to Allow for Increase in Ultimate Heat Sink Temp to 87 F Until 950930 ML20087D3751995-08-0707 August 1995 Application for Amends to Licenses DPR-77 & DPR-79,revising Time Constants for Overtemp Delta Temp & Overpower Delta Temp Equations 1999-08-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217F9551999-10-14014 October 1999 Application for Amends to Licenses DPR-77 & DPR-79,proposing Change to TS SRs & Bases to Incorporate ARC for Axial Primary Water Stress Corrosion Cracking at Dented Tube Support Plant Intersections ML20217E4211999-10-12012 October 1999 TS Change 99-15 to Licenses DPR-77 & DPR-79,providing Unisolation of Containment Penetrations Under Administrative Controls ML20212F4601999-09-23023 September 1999 Amends 246 & 237 to Licenses DPR-77 & DPR-79,respectively, Approving Request to Revise TSs to Allow Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20211K1521999-08-30030 August 1999 TS Change 99-10 to Licenses DPR-77 & DPR-79,providing Clarification to Current TS Requirements for Containment Isolation Valves ML20211M7261999-08-30030 August 1999 TS Change 99-08,for Amends to Licenses DPR-77 & DPR-79 to Provide Alternative to Requirement of Actually Measuring Response times.Marked-up & Revised TS Pages,Encl ML20209B7661999-06-30030 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,updating Current TS Requirements for RCS Leakage Detection & RCS Operational Leakage Specifications to Be Consistent with NUREG-1431 ML20196G4441999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Revise TS to Be Consistent with Rev to ISTS Presently Submitted to NEI TSTF for Submittal as Rev to NUREG-1431 ML20196F2121999-06-24024 June 1999 Application for Amends to Licenses DPR-77 & DPR-79,to Change TS Allowing Use of Fully Qualified & Tested Spare Inverter in Place of Any of Eight Required Inverters ML20195E9661999-06-0707 June 1999 Application for Amend to License DPR-79,increasing Max Allowed Specific Activity of Primary Coolant from 0.35 Microcuries/Gram Dose Equivalent I-131 to 1.0 Microcuries/ Gram Dose Equivalent I-131 for Plant Cycle 10 (U2C10) Core ML20207A5781999-05-20020 May 1999 Errata to Amend 163 to OL DPR-79 on 931126.SR 4.1.1.1.1.d Was Inadvertently Omitted from Pp 3/4 1-1 of Unit 2 TS ML20206E1341999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change Request 99-03, Main Control Room Emergency Ventilation Sys Verses Radiation Monitors. Change Adds LCOs 3.3.3.1 & 3.7.7 & NUREG-1431 Changes ML20206E1551999-04-29029 April 1999 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 99-04, Auxiliary Feedwater Suction Pressure Low Surveillance Frequency Rev. Change Deletes Surveillance ML20204H3991999-03-19019 March 1999 TS Change 99-01 to Licenses DPR-77 & DPR-79,relocating TS Associated with Electrical Equipment Protective Devices to Technical Requirements Manual ML20207D5941999-02-26026 February 1999 Application for Amend to Licenses DPR-77 & DPR-79,relocating TS 3.7.6, Flood Protection Plan & Associated Bases from TS to Plant TRM ML20207D6251999-02-26026 February 1999 Application for Amends to Licenses DPR-77 & DPR-79,revising TS to Provide for Consistency When Exiting Action Statements Associated with EDG Sets ML20206S0061999-01-15015 January 1999 TS Change 98-09 for Licenses DPR-77 & DPR-79,relocating TS 3.3.3.3, Seismic Instrumentation & Associated Bases from TS to Plant Technical Requirements Manual ML20199K5841999-01-15015 January 1999 Application for Amends to Licenses DPR-77 & DPR-79,adding New Action Statement to TS 3.1.3.2 That Would Eliminate Need to Enter TS 3.0.3 Whenever Two or More Individual RPIs Per Bank May Be Inoperable,While Maintaining Protection ML20195H6041998-11-16016 November 1998 Application for Amends to Licenses DPR-77 & DPR-79,revising EDG SRs by Adding Note to Allow SR to Be Performed in Modes 1,2,3 or 4 If Associated Components Are Already OOS for Testing or Maint & Removing SR Verifying Lockout Features ML20154H7201998-10-0808 October 1998 Supplemental Application for Amends to Licenses DPR-77 & DPR-79,changing TS to Add CRMP to Administrative Controls Section & Bases of TS ML20238F1051998-08-27027 August 1998 Application for Amend to License DPR-79,revising TS to Provide for Insertion of Limited Number of Lead Test Assemblies,Beginning W/Unit 2 Operating Cycle 10 Core ML20238F2981998-08-27027 August 1998 Revised Applications for Amends to Licenses DPR-77 & DPR-79, Replacing 72 H AOT of TS 3.8.1.1,Action b,w/7 Day AOT Requirement for Inoperability of One EDG or One Train of Edg.Response to RAI Included in Encl ML20249C6321998-06-26026 June 1998 Application for Amends to Licenses DPR-77 & DPR-79,lowering Specific Activity of Primary Coolant from 1.0 Uci/G Dose Equivalent I-131 to 0.35 Uci/G Dose Equivalent I-131,as Provided in GL 95-05 ML20248E9841998-05-28028 May 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,replacing Direct Ref to Nuclear QA Plan in TS Section 6.3.1,facility Staff Qualification,W/Actual Requirements Stated in TVA-NQA-PLN89-A ML20217N3411998-04-30030 April 1998 Application for Amends to Licenses DPR-77 & DPR-79,modifying TS Surveillance Requirement 4.4.3.2.1.b to Change Mode Requirement to Allow PORV Stroke Testing in Modes 3,4 & 5 W/Steam Bubble in Pressurizer Rather than Only in Mode 4 ML20203J1511998-02-25025 February 1998 Application for Amends to Licenses DPR-77 & DPR-79 to Change TS for Units 1 & 2,revising EDG Surveillance Requirements ML20202J6601998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79, Incorporating MSIV Requirements to Be Consistent W/Std TS (NUREG-1431) ML20202J7421998-02-13013 February 1998 TS Change 97-04 to Application for Amends to Licenses DPR-77 & DPR-79,relocating Snubber Requirements from Section 3.7.9 of TS to Plant Technical Requirements Manual ML20202J7101998-02-13013 February 1998 Application for Amends to Licenses DPR-77 & DPR-79,adding New LCO That Addresses Requirements for Main Feedwater Isolation,Regulating & Bypass Valves ML20198T4211998-01-21021 January 1998 Suppl TS Change 95-19 to Licenses DPR-77 & DPR-79,revising Title for President,Tva Nuclear & Chief Nuclear Officer to Generic Title of Chief Nuclear Officer ML20199K4441997-11-21021 November 1997 Application for Amend to License DPR-55,adding one-time Allowance Through Operating Cycle 9 to Surveillance Requirement 4.4.3.2.1.b to Perform Stroke Testing of PORVs in Mode 5 Rather than Mode 4,as Currently Required ML20211A3091997-09-17017 September 1997 TS Change 97-02 to Licenses DPR-77 & DPR-79,revising Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20137C8271997-03-19019 March 1997 Revised TS Change 96-01 to Licenses DPR-77 & DPR-79,revising Appropriate Specifications,Surveillances & Bases to Allow for Conversion from Westinghouse Fuel to Framatome Cogema Fuel ML20136J0251997-03-13013 March 1997 Application for Amends to Licenses DPR-77 & DPR-79,revising Allowed Enrichment of Fuel in TS Section 5.6.1.2 for New Fuel Pit Storage Racks from 4.5 to 5.0 Weight % U-235 IA-97-261, Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal1997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20211K5631997-03-0404 March 1997 Amend 220 to License DPR-77,authorizing Operation at Reactor Core Power Levels Not in Excess of 3,411 Megawatts Thermal ML20129D2561996-10-18018 October 1996 Application for Amends to Licenses DPR-77 & DPR-79,removing Existing Footnotes That Limit Application of Apc for Plant SG Tubes to Cycle 8 Operation for Both Units ML20129G7111996-09-26026 September 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Fire Protection License Conditions & Relocation of Fire Protection Tech Spec ML20113G2421996-09-20020 September 1996 Application for Amends to Licenses DPR-77 & DPR-79, Clarifying Work Shift Durations for Overtime Limits ML20117J3341996-08-28028 August 1996 Application for Amends to Licenses DPR-77 & DPR-79, Revising Psv & MSSV Setpoint Tolerance from Plus or Minus 1% to Plus or Minus 3% ML20117D0921996-08-22022 August 1996 Application for Amends to Licenses DPR-77 & 79 Changing Tss of Sqb Units 1 & 2 by Deleting Table 4.8-1, DG Reliability & Revising Sectio 3.8.1 to Allow a Once Per 18 Month 7 Day AOT for EDGs ML20117D2931996-08-21021 August 1996 TS Change 96-03 to Licenses DPR-77 & DPR-79,revising TS 3.7.1.3, Condensate Storage Tank, to Include New Mode of Applicability to Read Mode 4 When SG Relied Upon for Heat Removal ML20117D3271996-08-21021 August 1996 TS Change 96-06 to Licenses DPR-77 & DPR-79,removing Surveillance Requirement 4.8.1.1.1.b to Verify Ability to Transfer Unit Power Supply from Unit Generator Supported Circuit to Preferred Power Circuit ML20112H0361996-06-0707 June 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising Section 6, Administrative Controls, to Be More Closely Aligned W/Requirements of STSs ML20101N6981996-04-0404 April 1996 TS Change 96-01 to Licenses DPR-77 & DPR-79,allowing Use of Nuclear Fuel Provided by Framatome Cogema Fuels (Fcf). Proprietary & Nonproprietary Versions of Fcf TR Supporting TS Change 96-01 Encl.Proprietary Version of TR Withheld ML20096B3671996-01-0404 January 1996 Application for Amends to Licenses DPR-77 & DPR-79,revising TS Change 95-22,extending Radiation Monitoring Instrumentation Surveillance Period Per GL 93-05 ML20095F0271995-12-12012 December 1995 Application for Amend to License DPR-79,consisting of TS Change 95-23 Revising TS SRs & Bases to Incorporate Alternate S/G Tube Plugging Criteria at Tube Support Plate Intersections,Per GL 95-05 ML20095D5431995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,consisting of TS Change 93-09,revising Setpoints & Time Delays for AFW loss-of-power & 6.9 Kv Shutdown Board loss-of-voltage & degraded-voltage Instrumentation ML20095D5731995-12-0808 December 1995 Application for Amends to Licenses DPR-77 & DPR-79, Consisting of TS Change 95-20,extending Containment Spray & RHR Sys Nozzles Testing Period from 5 to 10 Yrs in Accordance W/Gl 93-05 ML20095D5811995-12-0808 December 1995 Application for Amend to Licenses DPR-77 & DPR-79,revising TSs to Implement Recent Rule Change to 10CFR50,App J ML20092E0191995-09-11011 September 1995 Application for Amend to License DPR-79,consisting of TS Change Request 95-13,rev 1 Re Extension of Response Time Surveillance Requirements for Unit Two Cycle 7 1999-09-23
[Table view] |
Text
I' y- . ..
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TA Tennessee Valley Authorny Post Office Box 2'100, Soddy-Daisy. Tennessee 37379 l
i June 24, 1999 l l
TVA-SQN-TS-99-05 10 CFR 50.90 i
U.S. Nuclear Regulatory Commission l ATTN: Document Control Desk l Washington, D. C. 20555 l
Gentlemen: '
In the Matter of ) Docket Nos. 50-327 Tennessee Valley Authority ) 50-328 I
1 SEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - TECHNICAL SPECIFICATION (TS) CHANGE No. 99-05, " CLARIFICATION OF ICE CONDENSER ICE WEIGHING REQUIREMENTS" In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a request for an amendment to SON's Licenses DPR-77 and 79 to change the TSs for Units 1 and 2.
The proposed change revises the Units 1 and 2 TSs to be consistent with the revision to the Improved Standard Technical Specifications (ISTS) presently submitted to the Nuclear Energy Institute Technical Specification Task Force (TSTF) for submittal as a revision to NUREG-1431. This proposed change was developed in coordination with the Westinghouse Owners Group - Ice Condenser Mini-Group (ICMG).
The ICMG represents all five domestic Westinghouse Ice Condenser Plants: Catawba, D. C. Cook, McGuire, Sequoyah, and Watts Bar Nuclear Stations. SON is considered to be the '
lead plant for the implementation of these revisions.
TVA has determined that there are no significant hazards /
considerations associated with the proposed change and that /
the change is exempt from environmental review pursuant to the provisions of 10 CFR 51.22 (c) (9) . The SON Plant of 9907010165'990624 PDR ADOCK 05000327 l P PDR
F~ . .
l 1
U.S. Nuclear Regulatory Commission Page 2 June-24, 1999 l
Operations Review Committee and the SQN Nuclear Safety Review Board have' reviewed this proposed change and determined that operation of SON Units 1 and 2,.in accordance with the proposed change, will not endanger the health and safety of the public. Additionally, in accordance.with 10 CFR
- 50. 91 (b) (1) , TVA is sending a copy of this letter to.the Tennessee State Department of Public Health.
~ Enclosure 1 to this letter provides the description and evaluation-ofEthe proposed change. 7his includes TVA's determination that the proposed change does not involve a significant hazards consideration, and is exempt from envircnmental review. Enclosure 2 contains copies of the appropriate TS pages from Units 1 and 2 marked up to show the proposed change. Enclosure 3 forwards the revised TS pages for Units 1.and 2 which incorporate the proposed change.
TVA requests that the revised TS be made effective within 45 days of NRC approval. If you have any questions about this
-change, please telephone me at (423) 843-7170 or J. D. Smith i
at (423) 843-6672.
e ,
.a?
3/
) as Li e ing and Industry Affairs Manager i
scribed a d sworn t fore me i on his 84 - day of /n. yL l
!$/ ~
J 01 _L< '
Notad/ PUblic' /
My Commission Expires October 9, 2002 Enclosures cc: -See page 3 i
E m..
y-.
U.S.' Nuclear Regulatory Commission Page 3 June 24, 1999 cc (Enclosures):
Mr. R. W. Hernan, Project Manager Nuclear. Regulatory Commission One White Flint, North 11555-Rockville Pike Rockville, Maryland 20852-2739 Mr. Michael H. Mobley, Director (w/o Enclosures)
Division of Radiological-Health Third Floor L&C Annex 401 Church Street Nashville, Tennessee 37243-1532 NRC Resident Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy-Daisy, Tennessee 37379-3624 Regional Administrator U.S. Nuclear Regulatory Commission
' Region II Atlanta Federal Center 61 Forsyth St., SW, Suite 23T85 Atlanta, Georgia 30303-3415 I
l
l .
ENCLOSURE 1 TENNESSEE VALLEY AUTHORITY l SEQUOYAH NUCLEAR PLANT (SQN)
^ UNITS 1 AND 2 l
l DOCKET NOS. 327 AND 328 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE 99-05 DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE I. DESCRIPTION OF THE PROPOSED CHANGE A change is requested to the current SON Units 1 and 2 TSs to provide for consistency with the revision to the Improved Standard Technical Specifications (ISTS) submitted to the Nuclear Energy Institute Technical Specification Task Force (TSTF) for submittal as a revision to NUREG-1431. This proposed change was developed in coordination with the Westinghouse Owners Group - Ice Condenser Mini-Group (ICMG). The ICMG represents all five domestic Westinghouse Ice Condenser Plants: Catawba, D. C. Cook, McGuire, Sequoyah, and Watts Bar Nuclear Stations. SON is considered to be the lead plant for the implementation of these revisions.
Specifically, the requested change reformats the discussion 1 in Surveillance Requirement (SR) 4.6.5.1.d.2, addressing the actions required if the ice baskets selected for weighing in a single ice condenser bay falls below the minimum required value, into a note at the beginning of the SR. The note further' clarifies that only 20 additional ;
baskets should be weighed even if more than one ice j condenser basket in a bay falls below the minimum required '
value. The proposed change also moves the ice basket ;
selection methodology in SR 4.6.5.1.d.2 from the TS SR to '
the bases. The final requested revision to SR 4.6.5.1.d.2 adds a statement clarifying that the total ice weight described in the limiting condition of operation (LCO) is applicable to the beginning of each operating cycle.
Revisions to the associated bases of this SR are also proposed to more accurately reflect the Improved Standard Technical Specification Bases as proposed in TSTF submittal.
II. REASON FOR THE PROPOSED CHANGE The purpose of making the proposed change is to provide for !
consistency between the SQN TS related to weighing ice baskets in the ice condenser and the proposed revision to the ISTSs. These changes implement the methodology agreed upon by the Ice Condenser Mini Group in accordance with the i El-1
. . l 4
. industry initiative related to ice condenser plants. The reformatting of the note to the TS SRs to address the actions required if one or more ice baskets selected for weighing in a single ice condenser bay falls below the minimum required value ensures a consistent interpretation of the requirements of the TSs. The proposed change to move the ice basket selection methodology from the TS SR to I the bases is consistent with the ISTS format that provides for required values to be addressed in the SR and descriptions or methodologies to be a part of the bases.
Providing a clarification in the TS SR and the associated bases that the ice condenser ice weight criteria is for the beginning of an operating cycle ensures consistent interpretation of the required weight since the overall ice weight in the ice condenser may fall below the specified value over an operating cycle due to sublimation. ,
(
III. SAFETY ANALYSIS The proposed change provides for consistency between the SON TS related to weighing ice baskets in the ice condenser and the proposed revision to the ISTSs described in the submittal from the TSTF. Reformatting the note to the TS SRs that addresses the actions required if one or more ice baskets selected for weighing in a single ice condenser bay falls below the minimum required value ensures a consistent interpretation of the requirements of the TSs and does not impact the intent or implementation of the TSs. The proposed change to move the ice basket selection i methodology from the TS SR to the bases is consistent with i the ISTS format that provides for required values to be addressed in the SR and descriptions or methodologies to be j a part of the bases. This revision does not affect the I implementation of the TS at SON since the procedural :
requirement will not be affected. Providing a clarification in the TS SR and the associated bases that the ice condenser ice weight criteria is for the beginning of an operating cycle ensures consistent interpretation of q the required weight since the overall ice weight in the ice j condenser may fall below the specified value over an operating cycle due to sublimation. This proposed revision does not affect the intent or implementation of the TSs at ,
SON. The revisions proposed above will not result in any l change in the design, maintenance, or operation of the ice i condenser and its associated support equipment. Nor does this revision result in deviation from the actions )
presently approved by the staff for response to the j associated LCO; therefore, it can be safely implemented at )
, SON.
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- NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION TVA has concluded that operation of SQN Units 1 and 2,
'in accordance with the proposed change to the technical ;
specifications (TSs), does not involve a significant j hazards consideration. TVA's conclusion is based on its evaluation, in accordance with 10 CFR 50.91(a) (1), of the three standards set forth in 10 CFR 50.92 (c) .
A. The proposed amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed TS amendments discussed below cannot increase the probability of occurrence of any analyzed accident because they are not the result or cause of l any physical modification to the ice condenser l structures, and for the current design of the ice condenser, there is no correlation between any credible failure and the initiation of any previously analyzed accident.
l Regarding the consequences of analyzed accidents, the preposed amendment provides for consistency with the ISTSs by: (1) requiring the actions if one or more ice condenser ice baskets are determined to weigh l below the minimum specified value to be made a part of the TS surveillance requirement (SR) instead of being located in the bases, and (2) relocating the Lce l basket selection methodology into the bases, 1his ensures consistent interpretation of the reqbirements ;
of the TS in accordance with the ISTSs. The clarification of the response required if one or more i ice baskets in a given bay are determined to be underweight ensures sufficient ice is maintained in each bay to prevent early meltout in a local zone following a design basis accident (DBA) and that the required overall ice weight is maintained in the ice condenser. The relocation of the ice basket selection methodology to the bases does not result in any change to the intent or implementation of this portion of the TSs since plant procedures ensure the requirements of the bases of the TSs are correctly implemented.
Additionally, the clarification that the weight requirement is applicable to the beginning of the cycle does not change the present intent of the TS, but ensures there is no confusion, since the weight at the end of the operating cycle may be less than that specified in the SR due to sublimation. This does not result in a change to the intent or implementation of l the TS since a sublimation allowance was provided in the original SR weight requirement. These clarifications do not result in any affect on plant El-3
equipment or operation and the actions taken during the implementation of the revised TS will be the same as' prior to the revision. Therefore, the clarification of these requirements will not increase the consequences of any accident previously evaluated.
B. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The inclusion of the action required for an underweight ice basket in the TS SR, instead of in the bases of the TS, provides for the consistent interpretation of the requirement. The clarification ;
of the response required if one or more ice baskets in !
a given bay are determined to be underweight ensures sufficient ice is maintained in each bay to prevent early meltout in a local zone following a DBA and that the required overall ice weight is maintained in the ice condenser. The relocation of the ice basket selection methodology to the bases does not result in any change to the intent or implementation of this portion of the TSs since plant procedures ensure the requirements of the bases of the TSs are correctly implemented. Additionally, the clarification that the weight requirement is applicable to the beginning of the cycle does not change the present intent of the TS, but ensures there is no confusion, since the ,
weight at the end of the operating cycle may be less I than that specified in the SR due to sublimation.
This does not result in a change to the intent or implementation of the TS since a sublimation allowance was provided in the original SR weight requirement.
The operation, design and maintenance of the ice condenser and its associated equipment will not change as a result of these clarifications. Therefore, the implementation of these clarifications will not create the possibility of accidents or equipment malfunctions of a new or different kind from any previously evaluated.
C. The proposed amendment does not involve a significant reduction in a margin of safety.
The proposed amendment allows for the consistent interpretation of the required actions if an ice basket is determined to weigh less than the required minimum. The inclusion of these actions in the TS SR instead of in the TS bases assures the correct actions will be taken as intended by the TSs. The clarification of the response required if one or more ice baskets in a given bay are determined to be El-4
underweight ensures sufficient ice is maintained in each bay to prevent early meltout in a local zona following a DBA and that the required overall ice weight is maintained in the ice condenser. The relocation of the ice basket : election methodology to the bases does not result in any change to the intent or implementation of this portion of the TSs since plant procedures ensure the requirements of the bases of the TSs are correctly implemented. Additionally, the clarification that the weight requirement is applicable to the beginning of the cycle does not change the present intent of the TS, but ensures there is no confusion, since the weight at the end of the operating cycle may be less than that specified in the SR due to sublimation. This does not result in a change'to the. intent or implementation of the TS since a sublimation allowance was provided in the original SR weight requirement. The proposed clarifications do not result in or have any affect on the operation, design, or maintenance of any plant equipment. Thus the design limits for the continued safe function of the containment structure following a DBA are not exceeded due to this change; therefore, the proposed amendment does not involve a reduction in a margin of safety.
V. ENVIRO!OENTAL IMPACT CONSIDERATION The proposed change does not involve a significant hazards consideration, a significant change in the types of or significant increase in the amounts of any effluents that may be released offsite, or a significant increase in individual or cumulative occupational radiation exposure. Therefore, the proposed change meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22 (c) (9) .
Therefore, pursuant to 10 CFR 51.22 (b) , an environmental assessment of the proposed change is not required.
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