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Category:OPERATING LICENSES & AMENDMENTS
MONTHYEARML20217D2641999-10-12012 October 1999 Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively, Deleting License Condition 2.C(22).A from License DPR-77 & License Condition 2.C.(16).b from License DPR-79 ML20217B3581999-10-0606 October 1999 Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively, Request Approval to Remove TS 3.7.6, Flood Protection Plan & Associated Bases from TS for Sequoyah Nuclear Power Plant, Units 1 & 2 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 ML20211N8811999-09-0707 September 1999 Amends 245 & 236 to Licenses DPR-77 & DPR-79,respectively, Requesting Approval to Remove Seismic Instrumentation Requirements & Associated Bases from SQN TSs for Units 1 & 2 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 ML20206G3691999-05-0404 May 1999 Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively, Adding New Action Statement to TS 3.1.3.2 That Eliminates Need to Enter TS 3.0.3 Whenever Two or More IRP Indicators Per Bank May Be Inoperable as Listed ML20205N0291999-04-12012 April 1999 Amend 234 to License DPR-79,revising Plant,Unit 2 TSs for Reactor Core by Adding Sentence at End of TS Section 5.3 Authorizing Installation of Limited Number of LTAs Containing Downblended U IAW TR BAW-2328 ML20204E8051999-03-16016 March 1999 Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively, Revising SQN Licenses by Deleting License Conditions 2.C.(23)F for Unit 1 & 2.C.(16)g for Unit 2 Which Authorizes TVA to Operate ML20206U4191999-02-0909 February 1999 Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively, Revising SQN TSs for EDG by Adding Note to SR 4.8.1.1.2.d.10 & Deleting SR 4.8.1.1.2.d.11 ML20198C0051998-12-16016 December 1998 Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively, Revising Sequoyah Nuclear Plant TSs by Extending AOT for Plant EDGs from 72 Hours to 7 Days ML20196C3721998-11-19019 November 1998 Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively, Revising TS 3.7.1.3 to Extend Limiting Condition for Operation of Condensate Storage Tanks to Mode 4 When SG Relied Upon for Heat Removal ML20196B0171998-11-19019 November 1998 Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively, Revising Plant,Units 1 & 2 TS SR 4.4.3.2.1 by Changing Mode Requirement to Allow power-operated Relief Valve Stroke Testing in Modes 3,4 & 5 with Steam Bubble in Pressurizer ML20195G3101998-11-17017 November 1998 Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively, Revising Plant TSs by Lowering Specific Activity Limit of Primary Coolant from 1.0 Uci/Gram Dose Equivalent iodine-131 to 0.35 Uci/Gram Dose Equivalent iodine-131 ML20238F2911998-08-28028 August 1998 Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively, Revising SQN TSs by Relocating Snubber Requirements from Section 3.7.9 of TS & Bases,To SQN Technical Requirements Manual ML20236S3301998-07-0101 July 1998 Amends 233 & 223 to Licenses DPR-77 & DPR-79,respectively, Revise Section 6, Administrative Controls, Snp TS by Relocating Certain QA Provisions from TS to TVA Nuclear Quality Assurance Plan ML20248L1911998-06-0808 June 1998 Amends 232 & 222 to Licenses DPR-77 & DPR-79,respectively,to Revise SQN TS by Adding New Limiting Condition for Operation 3.7.1.6 That Addresses Requirements for Main FW Isolation Valve Functions Required by SQN Accident Analysis ML20198P9051998-01-13013 January 1998 Amend 230 to License DPR-77,revising TS SR 4.4.3.2.1.b for Remainder of Cycle 9 to Perform Stroke Testing of power-operated Relief Valves in Mode 5 Rather than Mode 4 ML20217D7791997-09-29029 September 1997 Amends 229 & 220 to Licenses DPR-77 & DPR-79,respectively, Revises as-found Setpoint Tolerance Band for Pressurizer Code Safety Relief Valves & Ms Code Safety Relief Valves from 1% to 3% ML20211G1981997-09-23023 September 1997 Amends 228 & 219 to Licenses DPR-77 & DPR-79,respectively, Deleting TS Surveillance Requirement 4.8.1.1.1.b ML20210J5841997-08-12012 August 1997 Amends 227 & 218 to Licenses DPR-77 & DPR-79,respectively, Revising TS 3/4.3.3, Monitoring Instrumentation, TS 3/4.7.11, Fire Detection Sys, TS 3/4.7.12, Fire Barrier Penetrations & TS 6.2.2, Facility Staff ML20151L7911997-07-14014 July 1997 Amends 226 & 217 to Licenses DPR-77 & DPR-79,respectively, Change TS by Eliminating EDG Accelerated Testing & Special Reporting Requirements of TS 4.8.1.1.2.a ML20148S0491997-07-0101 July 1997 Amends 225 & 216 to Licenses DPR-77 & DPR-79,respectively, Revised TSs by Raising Allowable U-235 Enrichment Specified in Section 5.6.1.2 of Fuel Stored in New Fuel Pit Storage Racks from 4.5 to 5.0 Weight Percent ML20140E9951997-06-10010 June 1997 Amends 224 & 215 to Licenses DPR-77 & DPR-79,respectively, Revising TS 3.6.5 & Associated Bases to Lower Minimum TS Ice Basket Weight of 1,155 to 1,071 Pounds ML20137Y8831997-04-21021 April 1997 Amends 223 & 214 to Licenses DPR-77 & DPR-79,respectively, Revising Certain TS & Bases to Allow for Conversion of W Fuel to Framatome Cogema Fuel & Incorporating New License Conditions 2.C.(25) & 2.C.(18) ML20137R5941997-04-0909 April 1997 Amends 222 & 213 to Licenses DPR-77 & DPR-79,respectively, Revising TS 3.4.6.2,4.4.5.4 & 4.4.5.5 & Associated Bases to Permanently Incorporate Requirements Associated W/Sg Tube Inspections & Repair in Sequoyah Nuclear Plant,Units 1 & 2 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 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 ML20107N1091996-04-26026 April 1996 Amends 221 & 212 to Licenses DPR-77 & DPR-79 Revising Allowable Value for RCS Loss of Flow Reactor Trip Setpoint from Greater than or Equal to 89.4% to Greater than or Equal to 89.6% ML20101M5471996-04-0303 April 1996 Amend 211 to License DPR-79,revising TS Re Surveillance Requirements & Bases to Incorporate Alternate S/G Tube Plugging Criteria at TSP Intersections ML20100N5651996-03-0404 March 1996 Amends 220 & 210 to Licenses DPR-77 & DPR-79,respectively, Changing Surveillance Test Frequency Specified for Functional Tests of Containment,Fuel Storage Pool & Control Room Radiation Monitors from Monthly to Quarterly ML20100N1931996-03-0101 March 1996 Amends 219 & 209 to Licenses DPR-77 & DPR-79,respectively, Revising Setpoints & Time Delays for Auxiliary Feedwater loss-of-power & 6.9-kilovolt Shutdown Board loss-of-voltage & Degraded Voltage Instruments ML20097D4081996-02-0707 February 1996 Amends 218 & 208 to Licenses NPF-77 & NPF-79,respectively, Revising Frequency of CS Sys & RHR Sys Header Air or Smoke Surveillance Requirements ML20097F2021996-02-0505 February 1996 Amends 217 & 205 to Licenses DPR-77 & DPR-79,respectively, Implementing Change to 10CFR50,app J to Incorporate Option B,Voluntary performance-based Option,For Determining Frequency for Performing Type A,B & C Clrt ML20095F9831995-12-11011 December 1995 Amends 216 & 206 to Licenses DPR-77 & DPR-79,respectively, Relocating Heat Flux Hot Channel Factor Penalty from Surveillance Requirement 4.2.2.2.e.1 to Core Operating Limits Repts ML20094N5251995-11-21021 November 1995 Amends 215 & 205 to Licenses DPR-77 & DPR-79,respectively. Amends Address Operation W/Rod Urgent Failure Condition, Including Limited Operation W/One Control or Shutdown Bank Inserted 18 Steps Below Insertion Point ML20094D2231995-10-30030 October 1995 Amend 204 to License DPR-79.Amend Modifies License Condition 2.C.(17) by Extending Required Surveillance Interval to 960518 for Surveillance Requirement 4.3.2.1.3 for Certain Specified ESF Response Time Tests ML20092G6971995-09-13013 September 1995 Amends 210 & 200 to Licenses DPR-77 & DPR-79,changing TS 3.7.5.c to Allow Increase in Average Essential Rcw Supply Header Temp from 84.5 to 87 F Until 950930 ML20087L4631995-08-22022 August 1995 Amends 207 & 197 to Licenses DPR-77 & DPR-79,respectively, Delaying Implementation of Amends 182 & 174 Until Implementation Problems Addressed ML20085G4921995-06-13013 June 1995 Amends 202 & 192 to Licenses DPR-77 & DPR-79,respectively, Adds Limiting Condition for Operation That Allows Equipment to Be Returned to Svc Under Administrative Control to Perform Operability Testing & Establishes Time Interval ML20085J1721995-06-0606 June 1995 Corrected TS Page 6-11 to Amends 198 & 189 to Licenses DPR-77 & DPR-79,respectively,correcting Audit 6.5.2.8.i ML20084R5931995-06-0101 June 1995 Amends 201 & 191 to Licenses DPR-77 & DPR-79,respectively. Amends Revises Definition of Core Alteration & Quadrant Power Tilt Ratio of TS ML20084M9791995-05-30030 May 1995 Amend 200 to License DPR-77,modifying OL Condition 2.C Re Ice Condenser Surveillance Test Interval ML20084R6701995-05-30030 May 1995 Amends 199 & 190 to Licenses DPR-77 & DPR-79,respectively, Re Changes to TS to Revise SR for Power Range Neutron Flux Channel Calibration Frequency ML20083L1771995-05-10010 May 1995 Amends 198 & 189 to Licenses DPR-77 & DPR-79,respectively, Removing Frequencies Specified in TSs for Performing Audits & Deleting Requirements to Perform Rep,Psp & Safeguards Contingency Plan Reviews ML20087J3231995-04-28028 April 1995 Amends 197 & 188 to Licenses DPR-77 & DPR-79,respectively, Clarifying LCO Applicable to Dual Function of Containment Vacuum Relief Isolation Lines ML20082E4211995-04-0404 April 1995 Amends 196 & 187 to Licenses DPR-77 & DPR-79,respectively. Amends Revise TSs to Reduce High Reactor Power Level Setpoints When One or More Main Steam Safety Valves Inoperable & Incorporate Related Charges ML20078D7081995-01-24024 January 1995 Amends 194 & 185 to Licenses DPR-77 & DPR-79,respectively, Adding Permissive Statement to Surveillance Requirement 4.9.7.1 ML20077L1831995-01-0303 January 1995 Amend 193 to License DPR-77,extending Surveillance Interval Requirements to Coincide W/Cycle 7 Refueling Outage ML20077L2191994-12-27027 December 1994 Amends 192 & 184 to Licenses DPR-77 & DPR-79,respectively, Revising TS Re Cold Leg Injection Accumulators ML20076M6411994-11-0202 November 1994 Corrected TS Pp B 3/4 4-3 to Amend 189 to License DPR-77, Adding Info Inadvertenly Deleted 1999-09-07
[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 ML20217D2641999-10-12012 October 1999 Amends 248 & 239 to Licenses DPR-77 & DPR-79,respectively, Deleting License Condition 2.C(22).A from License DPR-77 & License Condition 2.C.(16).b from License DPR-79 ML20217E4211999-10-12012 October 1999 TS Change 99-15 to Licenses DPR-77 & DPR-79,providing Unisolation of Containment Penetrations Under Administrative Controls ML20217B3581999-10-0606 October 1999 Amends 247 & 238 to Licenses DPR-77 & DPR-79,respectively, Request Approval to Remove TS 3.7.6, Flood Protection Plan & Associated Bases from TS for Sequoyah Nuclear Power Plant, Units 1 & 2 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 ML20211N8811999-09-0707 September 1999 Amends 245 & 236 to Licenses DPR-77 & DPR-79,respectively, Requesting Approval to Remove Seismic Instrumentation Requirements & Associated Bases from SQN TSs for Units 1 & 2 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 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 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 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 ML20206G3691999-05-0404 May 1999 Amends 244 & 235 to Licenses DPR-77 & DPR-79,respectively, Adding New Action Statement to TS 3.1.3.2 That Eliminates Need to Enter TS 3.0.3 Whenever Two or More IRP Indicators Per Bank May Be Inoperable as Listed 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 ML20205N0291999-04-12012 April 1999 Amend 234 to License DPR-79,revising Plant,Unit 2 TSs for Reactor Core by Adding Sentence at End of TS Section 5.3 Authorizing Installation of Limited Number of LTAs Containing Downblended U IAW TR BAW-2328 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 ML20204E8051999-03-16016 March 1999 Amends 243 & 233 to Licenses DPR-77 & DPR-79,respectively, Revising SQN Licenses by Deleting License Conditions 2.C.(23)F for Unit 1 & 2.C.(16)g for Unit 2 Which Authorizes TVA to Operate 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 ML20206U4191999-02-0909 February 1999 Amends 242 & 232 to Licenses DPR-77 & DPR-79,respectively, Revising SQN TSs for EDG by Adding Note to SR 4.8.1.1.2.d.10 & Deleting SR 4.8.1.1.2.d.11 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 ML20198C0051998-12-16016 December 1998 Amends 241 & 231 to Licenses DPR-77 & DPR-79,respectively, Revising Sequoyah Nuclear Plant TSs by Extending AOT for Plant EDGs from 72 Hours to 7 Days ML20196C3721998-11-19019 November 1998 Amends 238 & 228 to Licenses DPR-77 & DPR-79,respectively, Revising TS 3.7.1.3 to Extend Limiting Condition for Operation of Condensate Storage Tanks to Mode 4 When SG Relied Upon for Heat Removal ML20196B0171998-11-19019 November 1998 Amends 239 & 229 to Licenses DPR-77 & DPR-79,respectively, Revising Plant,Units 1 & 2 TS SR 4.4.3.2.1 by Changing Mode Requirement to Allow power-operated Relief Valve Stroke Testing in Modes 3,4 & 5 with Steam Bubble in Pressurizer ML20195G3101998-11-17017 November 1998 Amends 237 & 227 to Licenses DPR-77 & DPR-79,respectively, Revising Plant TSs by Lowering Specific Activity Limit of Primary Coolant from 1.0 Uci/Gram Dose Equivalent iodine-131 to 0.35 Uci/Gram Dose Equivalent iodine-131 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 ML20238F2911998-08-28028 August 1998 Amends 235 & 225 to Licenses DPR-77 & DPR-79,respectively, Revising SQN TSs by Relocating Snubber Requirements from Section 3.7.9 of TS & Bases,To SQN Technical Requirements Manual 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 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 ML20236S3301998-07-0101 July 1998 Amends 233 & 223 to Licenses DPR-77 & DPR-79,respectively, Revise Section 6, Administrative Controls, Snp TS by Relocating Certain QA Provisions from TS to TVA Nuclear Quality Assurance Plan 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 ML20248L1911998-06-0808 June 1998 Amends 232 & 222 to Licenses DPR-77 & DPR-79,respectively,to Revise SQN TS by Adding New Limiting Condition for Operation 3.7.1.6 That Addresses Requirements for Main FW Isolation Valve Functions Required by SQN Accident Analysis 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 ML20198P9051998-01-13013 January 1998 Amend 230 to License DPR-77,revising TS SR 4.4.3.2.1.b for Remainder of Cycle 9 to Perform Stroke Testing of power-operated Relief Valves in Mode 5 Rather than Mode 4 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 ML20217D7791997-09-29029 September 1997 Amends 229 & 220 to Licenses DPR-77 & DPR-79,respectively, Revises as-found Setpoint Tolerance Band for Pressurizer Code Safety Relief Valves & Ms Code Safety Relief Valves from 1% to 3% ML20211G1981997-09-23023 September 1997 Amends 228 & 219 to Licenses DPR-77 & DPR-79,respectively, Deleting TS Surveillance Requirement 4.8.1.1.1.b ML20211A3091997-09-17017 September 1997 TS Change 97-02 to Licenses DPR-77 & DPR-79,revising Pressure Differential Surveillance Requirements for Containment Spray Pumps ML20210J5841997-08-12012 August 1997 Amends 227 & 218 to Licenses DPR-77 & DPR-79,respectively, Revising TS 3/4.3.3, Monitoring Instrumentation, TS 3/4.7.11, Fire Detection Sys, TS 3/4.7.12, Fire Barrier Penetrations & TS 6.2.2, Facility Staff ML20151L7911997-07-14014 July 1997 Amends 226 & 217 to Licenses DPR-77 & DPR-79,respectively, Change TS by Eliminating EDG Accelerated Testing & Special Reporting Requirements of TS 4.8.1.1.2.a 1999-09-07
[Table view] |
Text
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UNITED STATES g
NUCLEAR REGULATORY COMMISSION t
WASHWGTON, D. C. 20656
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TENNESSEE VALLEY AUTHORITY ECKETNO.50-327 SEQUOYAH NUCLEAR PLANT, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 121 License No. DPR-77 1.
The Nuclear Regulatory Comission (the Commission) has found that:
h A.
The application for amendment by Tennessee Va' ley Authority (the licensee) dated March 27, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),
and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be j
conducted in compliance with the Commission's regulations; j
D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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08090430 990733 pDR p
ADOCK 05000327 PNU 6.
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Accordingif the license is amended by che.nges to the Technical.
l Specifications as. indicated in the attachment to this license amendment.
j and paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby J
amended to read as follows l
)
(2) Technical Specifications
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The Technical Specifications contained in Appendices A and-B, as revised through Amendment No.121, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with l
the Technical Specifications.
3.
This license amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY C0lWISSION g
nu
%St zanne Black, Assistant Director j
for Projects
.c TVA Pro.jects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of I.ssuance: July 31, 1989
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. ATTACHMENT TO LICENSE AMENDMENT NO.121 FACILITYOPERATINGLICENSENO.DPR-J7 I,W DOCKET NO. 50-327 1
n, Revtse the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised-pages are identified by the captioned amendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 6-33 3/4 6-33 4
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CONTAINMENT SYSTEMS CONTAINMENT AIR RETURN FANS h$N 4
LIMITING CONDITION FOR OPERATION
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3.6.5.6 Two independent containment air return fans shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With one containment air return fan inoperable, restore the inoperable fan to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.6 Each containment air return fan shall be demonstrated OPERABLE:
At least once.per 92 days on a STAGGERED TEST BASIS by:
a.
1.
Verifying that the fan motor current is 3217.5 amps with the backdraft dampers closed, and 2.
Verifying that with the fan off, the air return fan damper opens when a torque of less than or equal to 68.1 inch-pounds is appied to the counterweight.
b.
At least once per 18 months by verifying that the air return fan starts on an auto-start signal after a 10 1 minute delay and operates for at least 15 minutes.
1 1
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SEQUOYAH - UNIT 1 3/4 6-33 Amendment No.12,121
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UNITE 3 8TATES f
p, NUCLEAR RE;ULATORY COMMISSION g
E CASHINGTON, C. C. 20665
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- o TENNESSEE VALLEY AUTHORITY DOCKET NO. 50-328 SEQUOYAH NUCLEAP. PLANT, UNIT 2 AMENDMENT TO FACILITY JPERATING LICENSE Amendment No.110 License No. DPR-79 I
1.
The Nuclear Regulatory Commission (the Commission) has found that:
yg u
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated March 27, 1989, complies with the standards and requirements of ttie Atomic Energy Act of 1954, as amended _ (the Act),
dnd the Commission'S rules and regulations set forth in 10 CFR-l Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the oublic, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or te the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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_the licent.e is amended by changes to the Technical Speciff ons as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) _ Technical Specifications l
l The Technical Specifications contained in Appendices A and. B, as revised through Amendment No. 110, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This ifcense amendment is effective as of its date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
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u an e ack, Assistant Director r
or Projects j
TVA Projects Division Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: July 31, 1939 l
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ATTACHMENT TO LICENSE AMENDMENT NO. 110 gg, FACILITY OPERATING LICENSE N0. DPR-79 4
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DOCKET N0.,50-328 Revise the Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned anendment number and contain marginal lines indicating the area of change. Overleaf pages* are provided to maintain document completeness.
REMOVE-INSERT 3/4 6-33 3/4 6-33*
3/4 6-34 3/4 6-34 l
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. CONTAINMENT SYSTEMS 1
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. DIVIDER BARRIER PERSONNEL ACCESS DOORS AND EQUIPMENT HATCHES i
4 LIMITING CONDITION FOR OPERATION 3.6.5.5 The personnel access doors and equipment hatches between the containment's upper and lower compartments shall be OPERABLE and closed.
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APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
With a personnel access door or equipment hatch inoperable or open except for personnel transit entry, restore the door or hatch to OPERABLE status'or to its closed position (as applicable) within I hour or be in at least HOT S1ANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.6.5.5.1 The personnel access doors and equipment hatches between the containment's upper and lower compartments shall be determined closed by a visual inspection prior to increasing the Reactor Coolant System T above 200 F and after each personnel transit entry when the Reactor Coolant 5fstem Tavg is a
above 200 F.
4.6.5.5.2 The personnel access doors and equipment batches between the containment's upper and lower compartments shall be determined OPERABLE by visually inspecting the seals and sealing surfaces of these penetrations and verifying no detrimental misalignments, cracks or defects in the sealing surfaces, or apparent deterioration of the sea' material:
Prior to final closure of the penetration each time it has been a.
opened, and b.
At least once per 10 years for penetrations containing seals fabricated from resilient materials.
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SEQUOYAH - UNIT 2 3/4 6-33
E-CONTAINMENT SYSTEMS
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. CONTAINMENT AIR RETURN FANS w.
LIMITING CONDIT50N FOR OPERATION l
3.6.5.6 Twa independent containment air return fans shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3 and 4.
ACTION:
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With one containment air return fan inoperable, restore the inoperable fan to l
OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
1 SURVEILLANCE REQUIREMENTS 4 6.5.6 Each containment air return fan shall be demonstrated OPERABLE:
At least once per 92 days on a STAGGERED TEST BASIS by:
a.
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Verifying that the fan motor current is 3217.5 amps with the backdraft dampers closed, and 2.
verifying that with the fan of f, the air return fan damper opens when a torque of less than or equal to 68.l inch-pounds is applied to the counterweight.
b.
At least once per 18 months by verifying that the air return fan starts on an auto-start signal after a 10 + 1 minute delay and operates for at least 15 minutes.
SEQUOYAH - UNIT 2 3/4 6-34 Amendment No.110
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