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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
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9 4
e Teorwee va%g AuthoMy Post omco Bcw 2000 LdA D+sy. Tentw:ssee 37379 J L Wnson Vce Presen. Seqeyan Ntclev P' ant November 9, 19s2 TS-SQN-72-15 10 CFR 50.90 U.S. Nuclear Regulatory Commission AT*IN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-327-Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR ptANT (SQN) - REQUEST FOR WAIVER OF COMPLIANCE FOR LIMITING CONDITION FOR OPERATION (LCO) 3.3.2.1 - EMERGENCY TECHNICAL SPECIFICATION CH/ME 92 MAINTENANCE ACTIVITY ON MAIN FEEDWATER REGULATING VALVE
Reference:
NRC letter to TVA dated October 30, 1992, " Temporary Waiver of Compliance - Sequoyah Unit 1" This letter serves to document TVA's request for, and NRC approval of, a waiver of con.pliance for Unit 1 LCO .3.3.2.1 to' support maintenance activities on the Loop 2 main 'eedwater regulating valve 1-FCV-3-48 while operating in Mode _1 at approximately 1.5 percent power. This request for waiver'is similar to the reference shown above and is required as a result of the overly conservative constraints of the current TSs.
Accompanying this waiver request is an emergency permanent license amendment request that, if granted, would preclude the potential for unit shutdown.while allowing for appropriate long-term capability to perform:
necessary feedwater valve maintenance and/or testing and to-prevent additional tnivers. IVA requested a waiver of the' feedeater ' isolation-actuation logic provision relative to the isolation response times applying to the main-feedwater regulating. valves ut.til_NRC staff approval-of the enclosed emergency TS change request.
Feedwater isolation capability intended by the technical specification (TS) will be.ensur ! during these maintenance and/or testing activities by maintaining'the associated manual isolation valve 1-3-541 (and-its associated bypass valve 1-3-545) tagged in the closed position.
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./2111oo+og 921109 DR- ADOCK 05000327.. .I
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.i e a U.S. Nuclear Re6ulatory Commission Page 2 November 9, 1992 ,
Feedwater. flow will be provided through the Loop 2 bypass regulating valve 1-FCV-3-48A. TS LCO 3.3.2.1, governing Fugineered Safety Feature Actuation System Instrumentation, through Tables 3.3-3 and 3.3-5, requir-e automatic isolation within defined response times utilizing the air-operated feedwater regulating valves. Necessary maintenance and testing of valve 1-FCV-3-48 will result in the inability to ensure isolation of this valve (when opened during the activities) within_those specified times utilizing any channel or train inputs. Only-the end device, air-operated regulating valve will be affected by these activities. The feedwater isolation (WI) actuation instrumentation and logic channels, including input to other protective actions, are unaffected. <
In accordance with~10 CFR 50.90, we are enclosing a requested amendment to Licenses DPR-77 and DPR-79-io chenge the TSs of SQN Units 1 and 2.
The proposed change will add the provisico to allow isolation of the feedwater flow path associated with FWI air-operated valves to satisfy the response time requirement for FW1. The proposed TS change is-identified in Enclosure 2. The justification for the ptoposed-TS change is provided in Enclosure 3. A proposed-determination of no significant hazards consideration performed pursuant to 10 CFR 50.92 is provided in Enclosure 4. This request has been reviewed and approved by the Plant; Operations Review Committee. The detailed justification ~for the waiver of compliance is provided in Enclosure 1.
These provisions are proposed to prevent unit shutdown to perform valve maintenance when the WI safety function can be otherwise fully satisfied. NRC has approved two waivers of compliance because of this TS problem. This change will eliminate the need for future waivers to perform maintenance or-testing on these valves.- TVA requests emergency processing of thic TS change request to prevent unnecessary challenges-to-plant safety systems resulting from unit shutdown.
This change request is being reviewed by TVA's Nuclear Safety Review
' Board (NSRB) in parallel with NRC review. Any changes resulting from the NSRB review will be'provided to NRC in a timely manner.
l.
' NRC approval of the waiver of comp 11anca for LCO 3.3.2.1 was provided verbally to TVA by G. C. Lainus, Assistant Director, Region II Reactors at 4: 12 p.m. Eastern standard -time _ on November 9, :1992.
l TVA is. additionally evaluating the viability of incorporating more extensive NUREG-1431 TS provisions as a_long-term enhancement. .It is
! expected _that any further changes resulting from that evaluatien would be L subm(tted tv NRC following the currently scheduled May 1993 SQN-NSRB' meeting.
l l
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U.S. Nuclear Regulatory Comnission Page 3 November 9, 1992 If you have any questions concerning this issue, please contact J. D. Smith at (615) 843-6672.
Sincerely,
- 5. r1A J L. Wilson _
Sworn this C to/and day ofsubscribed.de v before 1992 me s eqtt4ef Notary PubYic EY COMMISSION EX? IRES KPRit 9,1995 My Commission Expires
' Enclosures i cc (Enclosures):
Mr. D. E. LaBarge, Project Manager U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852
'Mr. Michael H. Mobley, Director (w/o Enclosure)
Division of Radiological Health 3rd Floor L L 0 Annex 401 Church Street Nashville, Tennessee 37203 NRC Resident-Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road Soddy Daisy, Tennessee 37379 Mr. B. A. Wilson, Project Chief.
U.S. Nuclear Regulatory Commiasion Region II 101 Marietta Street,.NW, Suite 2900 Atlanta, Georgia-30323 1
7 1 ENCLOSURE 1
. JUSTIFICATION FOR WAIVER OF COMPLIANCE FOR LIMITING CONDITION FOR OPERATION (LCO) 3.3.2.1 MEGEQWD Following the Unit 1 power escalation after the turbine / reactor trip on October 26, 1992, the unit operators observed indications that the Loop 2 main feedwater regulating valve 1-FCV-3-48 and its control loop were not ,
responding properly. Troubleshooting activities were-initially commenced on November 4,1992, with the reactor at approxir cely_60 percent power, when the operstor noted minor oscillations in the Loop 2 steam generator (S/G) level. Instrument Maintenu.e was dispatched to the valve and a minor adjustment was made to the volume booster. - While no ef fect was observed from this adjustment, the oscillations subsequently stopped.
On November 5 1M2, with the unit operating at approximately 100 percent power, Operations noted a decreasing water level in S/G No. 2 with feed-flow falling below steam flow. Upon noting the decreasing level, the main feedwater regulating valve on Loop 2 was placed in the manual position. Levels were eventually controlled with the main feedwater regulating valve in manual and the bypass regulating valve open in automatic. Further investigations on valve 1-FCV-3-48 have noted that air leakage at the bottom of the actuator spring case is noticeable.
Conversations with the valve manufacturer's representative have confirmed that an air leak caused by a degraded 0-ring between the shaft and bushing as the most.likely cause of the observed control problems.
S/G 1evel is currently being maintained with the main regulating valve in-(fixed position) manual with the bypass valvo controlling in automatic.
The current major concern is with the ability _of the r.it to withstand a secondary side transient, even with operator action, or further.
degradation of the existing condition. The identified condition of the valves does not affect ability to quickly close upon receipt of a feedwater isolation (FWI) signal.
The planned malatenance activities for the main regulating valve include evaluating and/or replacing the inner 0-ring (s), volume tooster, and air regulator. In addition, recalibration will- be. required along with the requisite postmaintenance response time testing. _ Provided that no unanticipatad problems occur, the estimated duration of the activity is approximately 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />. The replacement of the inner 0-rings on valve 1-FCV-3-48 and other related valve work may affect the valve's I response time. Thus, this activity will require the valve to be declared inoperable in a mode in which it is required to be operable.
During the conduct of the maintenance activities, the associated manual isolation valve 1-3-541 and its bypass will be tagged in the closed L position. This will maintain the Loop 2 main feedwater regulating valve L in'an isolated configuration throughout the maintenance activity, satisfying the intent nf.the LCO 3.3 2.1 feedwater isolation requirements. Reactor power will be reduced to approximately 15 percent. While at this power level, the feedwater bypass valve is capable of supplying adequate feedwater flow to the S/G.
Both the feedwater isolation and bypans regulating valve will be fully functional during this maintenance activity. Note that while the current-condition is isolated to valve 1-FCV-3-48, similar future activities could' occur on other feedwater regulating or bypass valvenfthat would necessitate applying similar constrainta.
Since the manual upstream valve 1-3-541 will be closed during necessary maintenance and testing activities, TVA has determined that operating in-deviation from the LCO requirements essociated with' response time for-closure of the feedwater regulating valves (Table 3.3-5, Items 2.c, 3.c, 6:c. end 8.b) would not placa the plant in an unsafe condition. The event leading to this situation was unforeseen; continued Unit 1 operr. tion in Mode 1 would not present a safety reduction; and timeliness of such NRC action is necessary to prevent the imposition of an unnecessary plant shutdown. The altuation resulting in this request is temporary and will be corrected. However, a permanent license amendment, including generic provisions, consistent with those provided by the intent of the recently approved FUREG-1431 is being proposed to NRC to provide continuing long-term capability to conduct necessary feedwater valve maintenar, e and/or testing. Accordingly, TVA has concluded that a request for g, 67
- waiver of compliance is warranted until NRC approval of the requesteu .ergency TS change. The detailed basis for the determination that operating in deviation of the LCO requirements would not place the plant in an unsafe condition is provided as follows.
SAFSIY_ ANALYSIS The feedwater system is a TVA Class -B safety system f rom the S/Cs (reference the Updated Final Safety Analysis Report (UFSAR] Figure 10.4.7-2) back through the motor-operated isolation valves (FCVs-3-33,
-47, -87, and -100) including.the check valves (3-508, -509, ~510, and
-511). This portion of the feedwater system is an integral part of the auxiliary feedwater system. Auxiliary feedwater capabilities will be unaffected by the subject activities. Located upstream of the isolation valve and check valve are the feedwater regulating valves (FCVs-3-35
-48, -90, and -103) and the bypass regulating valves (FCVs-3-35A, -48A,
-90A, and -103A). The regulating and bypass-valves are located in that portion of the feedwater system that is 1VA Class H, and are provided with individual manual isolation' valves immediately upstream.
The feedwater isolation signal-is part of the engineered safety features actuation system and serves to limit the core energy release in the case
- of a steamline break, to limit the magnitude of the reactor coolant system cooldown, and to prevent or mitigate the ef fect of excessive cooldown. This isolation, accompanied by a reactor trip, is accomplished by closure of redundant valves in the piping to each SG. The feedwater regulating valves (FCVs-3-35, -48, -90, and.-103) close in a nominal L 6.5 seconds.after receipt of a feedwater isolation signal. The feedwater isolation response time, which includes the closure time and all electronic delays of the feedwater regulating valves and bypass regulating valves (FCVs-3-35A, ~48A, -90A, and ~103A), is less than i
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9 8 seconds. The signal to initiate closure of the feedwater regulating valves is available from both Train A and B power. The Class 2 motor-operated feedwater isolation valves are designed to close within 7.5 seconds from receipt of the isolation signal. The isolation valves for S/Gs 1 and 3 are powered from Train A and S/Gs 2 and 4 are powered from Train B.- The feedwater bypass regulating valves associated with j S/cs 1 and 3 are powered from Train B, while those associated with S/Gs 2 !
and 4 are powered from Train A and are response time tested to ensure closure within the same timeframe as the main feedwater regulating v&ives.
The feedwater isolation valves are 16-inch, TVA Class B, motor-operated gate valves. The feedwater regulating valves are 16-inch, air-to-open spring-to-close, fail-closed control valves. The associated solenoid valves are connected to redundant trains of IE power. The feedwater bypass regulating valves serve as an solation valve when they are in s e rvice . These valves have the same design requirements as the j regulating valves and are served by 1E power. The manual isolation valve 1-3-541 is a 16-inch gate valve and is frequently used as a hold-order boundary for maintenance activities durin6 refueling outages.
Complete isolation of main'feedwater to all S/Gs occurs upon receipt of any of the following isolation signals from the reactor protection system:
- a. High-high S/G 1evel in any S/G - ,
- h. Safety injection signal
- c. Reactor trip coincident with low-reactor coolant T,yg In addition, the valves will remain in the 'losed position if the reactor protection signals are reset; however, each valve can be opened or closed manually after the reactor protection system isolation signals are reset.
The assumptions utilized in the determination of the isolation time for accident analysis purposes are:
- 1. SQN is an ice condenser plant that by design reduces peak pressures in the containment, both in magnitude and duration.
- 2. The unisolatable volumu of the feedwater system between the regulating valves and the steam generators is no more than 104 cubic -
feet, which is less than the maximum volume of 150 cubic feet recommended by Westinghouse Electr! Corporation.
- 3. The main feedwater pumps are tripped on a feedwater isolation signal.
The feedwater regulating valves are the primary mechanism for feedwater isointion assumed in the loss of coolant accident (LOCA) and non-LOCA analyses. Closure of the feedwater isolation valves is considered a backup mechanism for isolation in the analyses to the regulating valves in conjunction with the tripping of the main feedwater pumps.
~4-The ability to utilize the manual isolation valve to perform the-isolation function to allow maintenance on the regulating (and bypass) valves is considered acceptable. The closure of the manual valve (1-3-541) just upstream of the Loop 2 main feedwater regulating valve provides'an acceptable alternative for meeting the intent of LOO 3.3.2.1-during the waivered period. The open feedwater isolation valve and controlling bypass regulating valve will remain fully operational during this activity and their isolation time is unaf fected.
1YAJEQUESUDILWAIVER OF COMPLI4liC.E TVA requests a waiver of compliance for LCO 3.3.2.1, Iable 3.3-3, Items 1.b and 5.b regardin6 the aetomatic actuation logic for feedwater isolation function as applied to the main feedwater regulating valves as required by Table 3.3-5, Items 2.c, 3.c, 6.c and 8.b. LCO 3.3.2.1 requires the feedwater isolation function to be operable in operating modes. The planned maintenance activities will require the Loop 2 regulating valve to be declared inoperable while in the applicable modes, 4 deviating from the LCO requirement to maintain the automatic and manual isolation capability of this valve within the response times provided in Table 3.3-5.
TVA requested a waiver of the feedwater isolation actuation logic provision relative to the isolation response times applying to the main feedwater regulating valves pending staff approval of the proposed- .
emergency TS change. Feedwater isolation capability intended by the technical specification (TS) will be ensured during these activities by maintaining associated manual isolation valve 1-3-541 (and its associated bypass-line 1-3-545) in the closed position. TS LCO 3.3.2.1, governing Engineered Safety Feature Actuation System Instrumentation, through Tables 3.3-3 and 3.3-5, requires automatic. isolation within defined response times utilizing the air-operated feedwater regulating valves.
Necessary maintenance and testing of valve 1-FCV- 3-43 will result in the inability to ensure isolation of this valve (wher. opened during the
, activities) within those sper."'ied times utilizing any channel or train inputs.
Only the end device, air-operated regulating valve will be affected by q this activity. The feedwater isolation actuaticn instrumentation and i logic channels, including input to other protective actions, are unaffected. The actuation system instrumentation TS is conservatively applied to the subject situation involving the' actuation end device (regulating valve).
The requested waiver was determined to have no safety significance because the intended isolation capability of the feedwater system will be
. maintained by the closed manual isolation valve and. operable FWI and l bypass regulating valve for the duration of the subject activity.
Accordingly, the requested waiver cannot result in an: increase in the 1
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probability or' consequences of a previously evaluated accident, cannot create the possibility of a new accident, and cannot reduce the margin of ,
safety. Therefore, the action does not involve a significant hazards consideration. Similarly, the waiver does not involve an unreviewed environmental question because it does not increase any adverse ,
environmental impacts, change effluents or power levels, or result in unreviewed environmental mattere.
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