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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
,
. 1 Tennessee Vahey Authonty Post Office Box 2000 Soddv-Daisy. Tennessee 37379 i
1 1
January 15, 1999 l i
l TVA-SON-TS-98-09 10 CFR 50.90 i
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555 Gentlemen:
In the Matter of ) Docket Nos. 50-327 ;
Tennessee Valley Authority ) 50-328 SEQUOYAH NUCLEAR PLANT (SQN) - UNITS 1 AND 2 - TECHNICAL SPECIFICATION (TS) CHANGE NO. 98-09, " RELOCATION OF SEISMIC INSTRUMENTATION" In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a request for an amendment to Licenses DPR-77 and DPR-79 to change the TSs for Units 1 and 2. The proposed change relocates TS 3.3.3.3, " Seismic /
Instrumentation," and the associated bases from the TS to the SON Technical Requirements Manual (Tmi) . This change does /
not alter the current requirements for operability or surveillance testing of the seismic instrumentation, and future revisions of these requirements will require an pg 7gf evaluation in accordance with 10 CFR 50.59.
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 SQN Plant 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.
~
9901270156 990115 PDR ADOCK 05000327 P PDR' -
- . - - .~ ;
l l l l U.S. Nuclear Regulatory Commission Page 2
,. January 15, 1999 Enclosure 1 to this letter provides the description and evaluation of the proposed change. This includes TVA's determination that the proposed change does not involve a significant hazards consideration, and-is exempt from environmental 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 l
! for Units 1 and 2, which incorporate the proposed change. I L
l NRC review and approval of the proposed TS change is l requested prior to August 2, 1999. This date is the i
projected start date for field work associated with a plant ,
upgrade for SON's seismic instrumentation. j 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. i Smith at (423) 843-6672.
Sincerely, f
ghj 1 =. .
Pe as Manager of Licensing Subscribed d sworn before me n -his ./ day of ()/y 7-. /1/2 M y l
.lb0/ 1 AM
~/
~
15tary/ fubli'c ' /
My Commission Expires October 9, 2002 Enclosures l cc: See page 3 l i 1
I .- .
i 1
! U.S. Nuclear Regulatory Commission Page 3
,, January 15, 1999 1
cc (Enclosures): l Mr. R. W. Hernan, Project Manager Nuclear Regulatory Commission
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 1
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
ENCLOSURE 1 I I TENNESSEE VALLEY AUTHORITY ,
SEQUOYAH NUCLEAR PLANT (SQN) l UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 PROPOSED TECHNICAL SPECIFICATION (TS) CHANGE TS-98-09 DESCRIPTION AND EVALUATION OF THE PROPOSED CHANGE l
l I. DESCRIPTION OF THE PROPOSED CHANGE The proposed change will remove the seismic instrumentation i requirements and the associated Bases from the TSs for l Units 1 and 2. TVA will relocate the seismic instrumentation requirements to the SON Technical ,
Requirements Manual (TRM). In addition, the appropriate TS l index pages have been revised to reflect this change. i II. REASON FOR THE PROPOSED CHANGE TVA requests the proposed change to remove requirements from the SON TSs that do not meet the criteria in 10 CFR 50.36. TVA's proposed change is provided in j accordance with the guidance in NRC Generic Letter (GL) -
95-10, " Relocation of Selected Technical Specifications Requirements Related to Instrumentation," dated December 15, 1995. NRC GL 95-10 refers to the Commission's Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors, published in the Federal Register, (58 FR 39132). The NRC Final Policy Statement states that TS requirements that do not meet any of the screening criteria for retention may be proposed for removal from the TS and relocated to licensee-controlled documents, such as the Final Safety Analysis Report or TRM.
TVA's proposed change will allow revisions to the seismic instrumentation, in accordance with 10 CFR 50.59, without requiring a License Amendment Request and adds flexibility to processing necessary changes.
TVA is planning to upgrade SON's seismic instrumentation starting in August 1999. The proposed upgrade includes l replacement of the current analog seismic recorders and central recording and playback units with a new digital i system.
III. SAFETY ANALYSIS SON's seismic instrumentation is designed to record data on seismic ground motion and provide data on the frequency and amplitude relationship of the response of major structures and systems. SON's system is designed for compliance with NRC Regulatory Guide 1.12, Revision 1, " Instrumentation for Earthquakes."
El-1
,- , Currently, SON TSs provide the limiting conditions of operation (LCO) and surveillance requirements (SRs) to verify the operability of seismic instrumentation. The operability of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluates the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. The current SRs include the conduct of periodic channel checks, channel calibrations, and channel functional tests. The TS Bases contains the basis for requiring seismic instrumentation.
TVA's proposed TS change is consistent with the guidance of NRC GL 95-10 and Standard TS (NUREG-1431). In NUREG-1431, there are no seismic instrumentation TS requirements because this instrumentation does not meet the criteria in 10 CFR 50.36. NRC GL 95-10 provides guidance for relocating selected instrumentation requirements that do not meet the criteria from 10 CFR 50.36. In addition, TVA evaluated SON's current seismic instrumentation TS requirements against the criteria of 10 CFR 50.36. The following discussions address the applicability of the 10 CFR 50.36 criteria to SON's TS for seismic instrumentation:
Criterion 1: Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.
Seismic instrumentation is used to record data for use in evaluating the effect of a seismic event. The instrumentation is not used to mitigate a design basis accident (DBA) or transient. SQN's seismic instrumentation is not installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal j degradation of the reactor coolant pressure boundary. I Accordingly, the SON seismic instrumentation does not j satisfy Criterion 1. l Criterion 2: A process variable, design feature or operating restriction that is an initial condition of a l Design Basis Accident (DBA) or Transient that either assumes the failure of or presents a challenge to the ;
integrity of a fission product barrier.
SON's seismic instrumentation is not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier. Therefore, the SQN seismic instrumentation does not satisfy Criterion 2.
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,. , Criterion 3: A structure, system or component that is part of the primary success path and which functions or actuates to mitigate a DBA or Transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
SQN's seismic instrumentation is not assumed to function in !
the safety analysis. The instrumentation is not a
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structure, system or component that is part of the primary I success path for accident mitigation. In addition, seismic !
instrumentation does not function or actuate to mitigate a !
DBA or Transient that either assumes the failure of or '
presents a challenge to the integrity of a fission product barrier. Accordingly, seismic instrumentation does not satisfy Criterion 3. l Criterion 4: A structure, system or component, which operating experience or probabilistic safety assessment has shown to be significant to public health and safety.
Operational experience or probabilistic safety assessment l have not shown the SON seismic instrumentation to be i significant to the public health and safety. Therefore, ;
the instrumentation does not satisfy Criterion 4.
The proposed relocation of the seismic instrumentation f requirements to the SQN TRM is acceptable based of the :
above discussions. In accordance with 10 CFR 50.59, the !
relocated requirements will be controlled to ensure changes i are not implemented that would reduce the functionality or testing of SQN's seismic instrumentation without prior NRC review.
IV. NO SIGNIFICANT HAEARDS CONSIDERATION DETERMINATION TVA has concluded that operation of SQN Units 1 and 2, in accordance with the proposed change to the TS, does not involve a significant hazards consideration. TVA's conclusion is based on its evaluation, in accordance with i 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 1 accident previously evaluated. I l
The proposed revision to the TS relocates the !
requirements for SON seismic instrumentation without )
changing the current requirements. TVA does not '
consider the instrumentation to be the source of any accident; therefore, this administrative relocation of the requirements will not increase the possibility of El-3
I i an accident. The capability of the seismic
, ,- ,- instrumentation will continue to provide the same function for data collection. Changes to the i relocated requirements will be processed, in
! accordance with 10 CFR 50.59, to ensure the seismic instrumentation functions will be properly maintained.
Therefore, the proposed relocation of the seismic instrumentation requirements will not increase the consequences of an accident.
B. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The SON seismic instrumentation is used to record data ,
for use in evaluating the effect of a seismic event.
This instrumentation is not associated with accident mitigation or previously evaluated accidents and would '
not be the initiator of any new or different kind of accident. The proposed change does not alter the current functions of SON's seismic instrumentation; therefore, this proposed change will not create the possibility of a new or different kind of accident.
C. The proposed amendment does not involve a significant reduction in a margin of safety.
The requirements for SON's seismic instrumentation are unchanged by the proposed relocation of the requirements to the SON TRM. The function of the seismic instrumentation and SRs to ensure operability of the instrumentation remains unchanged. Any future changes to these requirements will be evaluated, in accordance with 10 CFR 50.59, to ensure acceptability and NRC review as required. Accordingly, the proposed change will not result in a reduction in a margin of safety.
V. ENVIRONMENTAL 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 j may be released offsite, or a significant increase in
- individual or cumulative occupational radiation exposure. l 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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