|
---|
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
-
acn p
'l UNITED STATES a
1 l
g
}
NUCLEAR RESULATORY COMMISSION O[
WASHINGTON, D.C. 206E0001 o,
o 4.....g TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-327 SE0V0VAH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 224 License No. DPR-77 i
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the licensee) dated August 22, 1996 as supplemented March 28, 1997, 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; 8.
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 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 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.
l 9706120276 970610 i
PDR ADOCK 05000327 I
P PDR
4 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-77 is hereby amended to read as follows:
(2) Technical Specifications
~
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 224, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION h,hc r
c-Frederick J. Hebdon, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Changes to the Technical 1
Specifications Date of Issuance: June 10, 1997 i
=.
ATTACHMENT TO LICENSE AMENDMENT NO. 224 FACILITY OPERATING LICENSE N0. DPR-77 DOCKET NO. 50-327 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 amendment number and contain marginal lines indicating the area of change.
l REMOVE INSERT l
3/4 6-26 3/4 6-26 3/4 6-27 3/4 6-27 B 3/4 6-4 B 3/4 6-4 l
t f
l i
i
CONTAINMENT SYSTEMS 3 /4. 6. 5 ICE CONDENSEP
)
ICE BED l
LIMITING CONDITION FOR OPERATION l
s.o.a.s.
xne sce cea snass ce urtnanaz wasns The stored ice having a boron concentration of at least 1800 ppm a.
boron as sodium tetraborate and a pH of 9.0 to 9.5, b.
Flow channels through the ice condenser, A maximum ice bed temperature of less than or equal 27'F, c.
d.
A total ice weight of at least 2,082,024 pounds at a 95% level of cenfidence, and i
1 e.
1944 ice baskets.
APPLICABILITY: MODES 1, 2,
3 and 4.
ACTION:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-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 SEUTDOWN 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 4.6.5.1 The ice condenser shall be determined OPERABLE:
At least ence per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using the ice bed temperature a.
l monitoring system to verify that the maximum ice bed temperature is less than or equal to 278F.
b.
At least once per 12 months by:
Verifying, by visual inspection of a representative random sample of at least 54 flow passages (33 percent) per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck floor grating, or past the lower inlet plenum support structures and i
turning vanes is less than or equal to 15-percent blockage of the total flow area in each bay, with a 95-percent level of confidence.
If the summation of blockage from the sample fails to meet the acceptance criteria, then 100 percent of the passages of that bay shall be inspected.
If the 100-percent inspection fails to meet the acceptance criteria, then the flow passages shall be cleaned to meet the acceptance criteria. Each flow passage that is cleaned will be 1
reinspected. Any inaccessible flow passage that is not inspected will be considered blocked.
i SEQUOYAH - UNIT 1 3/4 6-26 Amendment No.
4, 126, 131,224 l
CONTAINMENT SYSTEMS SURVEILIANCE REQUIREMENTS (Continued)
At least once per 40 months by lifting and visually inspecting the c.
l accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verifying that the ice baskets are free of detrimental structural wear, cracks, corrosion or other damage.
The ice baskets shall be raised at least 10 feet for this inspection.
d.
At least once per 18 months by:
1.
Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration of at least 1800 ppm as sodium tetraborate and a pH of 9.0 to 9.5.
2.
Weighing a representative sample of at least 144 ice baskets and verifying that each basket contains at least 1071 lbs of ice.
,l The representative sample shall include 6 baskets from each of the 24 ice condenser bays and shall be constituted of one basket each from Radial Rows 1, 2, 4,
6, 8 and 9 (or from the same row of an adjacent bay if a basket from a designated row cannot be obtained for weighing) within each bay.
If any basket is found to contain less than 1071 pounds of ice, a l
representative sample of 20 additional baskets from the same bay shall be weighed. The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1071 pounds / basket at a 95% level of confidence.
l t
The ice condenser shall also be subdivided into 3 groups of baskets, as follows: Group 1 - bays 1 through 8, Group 2 - bays j
9 thrcugh 16, and Group 3 - bays 17 through 24.
The minie.um average ice weight of the sample baskets from Radial Rows 1, 2,
i 4 / 6, 8 and 9 in each group shall not be less than 1071 pcunds/ basket at a 95% level of confidence.
l The minimum total ice condenser ice weight at a 95% level of confidence shall be calculated using all ice basket weights determined during this weighing program and shall not be less than 2,082,024 pounds.
l l
SEQUOYAH - UNIT 1 3/4 6-27 Amendment No.
4, 98, 131,224
i CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL The OPERABILITY of the equipment and systems required for the detection and control of hydrogen gas ensures that this equipment will be available to maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions.
Either recombiner unit or the hydrogen mitigation system, consisting of 68 hydrogen ignitions per unit, is capable of controllin reactions,g the expected hydrogen generation associated with 1) zirconium-water
- 2) radiolytic decomposition of water and 3) corrosion of metals within containment.
effects of an accident as described in Regulatory Guide 1.7,These hydrogen control sy
" Control of Combustib2e Gas Concentrations in Containment Following a LOCA",
Revision 2 dated November 1978.
of the accident monitoring instrumentation in Specification 3.3.3.7 and areThe hydro i
i designated as Type A, Category 1 in accordance with Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA.
This mixing action will prevent
)
localized accumulations o:! hydrogen from exceeding the flammable limit.
The operability of at least 66 of 68 ignitors in the hydrogen mitigation system will maintain an effective coverage throughout the containment.
This system of ignitors will initiate combustion of any significant amount of hydrogen released after a degraded core accident.
This system is to ensure burning in a centrolled manner as the hydrogen is released instead of. allowing it to be ignited at high concentrations by a random ignition source.
3 /4. f. 5 ICE CCt7 DENSER The requirements assceiated with each of the components of the ice cen-denser ensure that the overall system will be available to provide sufficient pressure suppression capability to limit the containment peak pressure tran-sient to less than 12 psig during LOCA conditions.
3/4.6.5.1 ICE BED The OPERABILITY of the ice bed ensures that the required ice inventory will 1) be distributed evenly through the containment bays, 2) contain suffi-cient boron to preclude dilution of the containment sump following the LOCA and
- 3) contain sufficient heat removal capability to condense the reactor system volume released during a LOCA.
These conditions are consistent with the assumptions used in the accident analyses.
The minimum weight figure of 1071 pounds of ice per basket contains a 15%
l conservative allowance for ice loss through sublimation which is a factor of 15 higher than assumed for the ice condenser design.
The minimum weight figure of 2,082,024 pounds of ice also contains an additional it conservative allowance to account for systematic error in weighing instruments.
In the SEQUOYAH - UNIT 1 B 3/4 6-4 Amendment No.
4, 5, 131, 149, 224
j gs W EQu
[
k UNITED STATES g
}
NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20666 4 001
\\ ***,
p$
TENNESSEE VALLEY AUTHORITY DOCKET N0. 50-328 SE000YAH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.215 License No. DPR-79 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Tennessee Valley Authority (the j
licensee) dated August 22, 1996 as supplemented March 28, 1997, 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 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 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.
I,
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment.
Paragraph 2.C.(2) of Facility Operating License No. DPR-79 is hereby amended to read as follows:
(2) Technical Specifications
~
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 215, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance, to be implemented no later than 45 days of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION M
vt
~-
Frederick J. Hebdon, Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
- 1. Changes to the Technical Specifications Date of Issuance:
June 10,1997 l
i i
l ATTACHMENT TO LICENSE AMENDMENT NO. 215 l
FACILITY OPERATING LICENSE NO. DPR-79 DOCKET NO. 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 umendment number and contain marginal lines indicating the area of change.
REMOVE INSERT 3/4 6-27 3/4 6-27 3/4 6-28 3/4 6-28 B 3/4 6-4 8 3/4 6-4 i
l
CONTAINMENT SYSTEMS 3/4.6.5 _ ICE CONDENSER l
ICE BED LIMITING CONDITION FOR OPERATION 3.6.5.1 The ice bed shall be OPERABLE with:
The stored ice having a boron concentration of at least 1800 ppm a.
boron as sodium tetraborate and a pH of 9.0 to 9.5, b.
Flow channels through the ice condenser, A maximum ice bed temperature of less than or equal to 27*F, c.
d.
A total ice weight of at least 2,082,024 pounds at a 95% level of confidence, and e.
1944 ice baskets.
l APPLICABILITY: MODES 1, 2, 3 and 4.
i i
ACTION:
With the ice bed inoperable, restore the ice bed to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-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 />.
l FURVEILLANCE RECUIREMENTS 4.6.5.1 The ice condenser shall be determined OPERABLE:
At lea'st once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> by using the ice bed temperature a.
monitoring system to verify that the maximum ice bed temperature is less than or equal to 27'F.
j b.
At least once per 12 months by:
Verifying, by visual inspection of a representative random sample of at least 54 flow passages (33 percent) per ice condenser bay, that the accumulation of frost or ice on flow passages between ice baskets, past lattice frames, through the intermediate and top deck l
l floor grating, or past the lower inlet plenum support structures and turning vanes is less than or equal to 15-percent blockage of the l
total flow area in each bay, with a 95-percent level of confidence.
If the summation of blockage from the sample fails to meet the acceptance criteria, then 100 percent of the passages of that bay shall be inspected.
If the 100-percent inspection fails to meet the acceptance criteria, then the flow passages shall be cleaned to mest the acceptance criteria.
Each flow passage that is cleaned will be reinspected.
Any inaccessible flow passage that is not inspected will be considered blocked, i
j
(
SEQUOYAH - UNIT 2 3/4 6-27 Amendment No. 80, 118,215
CONTAINMENT SYSTEMS SURVEIIIANCE REQUIREMENTS (Continued)
At least once per 40 months by lifting and visually inspecting the c.
accessible portions of at least two ice baskets from each 1/3 of the ice condenser and verif mental structural wear,ying that the Ace baskets are free of detri-cracks, corrosion or other. damage. The ice baskets shall be raised at least 10 feet for this inspection.
d.
At least once per 18 months by:
1.
Chemical analyses which verify that at least 9 representative samples of stored ice have a boron concentration of at least 1800 ppm as sodium tetraborate and a pH of 9.0 to 9.5.
2.
Weighing a representative sample of at least 144 ice baskets and verifying that each basket contains at least 1071 lbs of ice.
The representative sample shall include 6 baskets from each of the 24 ice condenser bays and shall be constituted of one basket each from Radial Rows 1, 2, 4, 6, 8 and 9 (or from the same row of an adjacent bay if a basket from a designated row cannot be obtained for weighing) within each bay.
If any basket is found t
to contain less than 1071 pounds of ice, a representative sample l
of 20 additional baskets from the same bay shall be weighed.
4 i
The minimum average weight of ice from the 20 additional baskets and the discrepant basket shall not be less than 1071 3
pounds / basket at a 95% level of confidence.
l i
The ice condenser shall also be subdivided into 3 groups of l
baskets, as follows:
Grcup 1 - bays 1 through 8. Grcup 2 -bays l
9 through 16, and Group 3 - bays 17 through 24.
The minimum i
average ice weight of the sample baskets from Radial Rows 1, 2, 4,
6, 8 and 9 in each group shall not be less than 1071 i
pounds / basket at a 95% level of confidence.
The minimum total ice condenser ice weight at a 95% level of confidence shall be calculated using all ice basket weights determined during this weighing program.and shall nbt'be less than 2,082,024 pounds.
]
i f
1 SEQUOYAH - UNIT 2' 3/4 6-28 Amendment No. 80, 87, 114 21 5 March 2, 1990
=_ - _- -.- -
CONTAINMENT SYSTEMS BASES 3/4.6.4 COMBUSTIBLE GAS CONTROL l
)
The OPERABILITY of the equipment and systems required for the detection l
and control of hydrogen gas ensures that this equipment will be available to i
maintain the hydrogen concentration within containment below its flammable limit during post-LOCA conditions. Either recombiner unit or the hydrogen I
mitigation system, consisting of 68 hydrogen ignitors per unit, is capable of controlling the expected hydrogen generation associated with 1) zirconium-water reactions, 2) radiolytic decomposition of water and 3) corrosion of metals within containment. These hydrogen control systems are designed to mitigate the effects of an accident as described in Regulatory Guide 1.7,
" Control of Combustible Gas Concentrations in Containment Following a LOCA," Revision 2, dated November 1978.
of the accident monitoring instrumentation in Specification 3.3.3.7 and areThe hydrogen designated as Type A, Category 1 in accordance with Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980.
The hydrogen mixing systems are provided to ensure adequate mixing of the containment atmosphere following a LOCA.
This mixing action will prevent localized accumulations of hydrogen from exceeding the flammable limit.
The operability of at least 66 of 68 igniters in the hydrogen control distributed ignition system will maintain an effective coverage throughout the containment.
This system of ignitors will initiate combustion of any signifi-cant amount of hydrogen released after a degraded core accident.
This system l
is to ensure burning in a controlled manner as the hydrogen is released instead of allcwing it to be ignited at high cencentrations by a random igni, tion i
rource.
1 2/4.6.5 ICE CONDENSER l
The requirements associated with each of the components of the ice condenser ensure that the overall system will be available to provide sufficient pressure suppression capability to limit the containment peak pressure transient to less than 12 psig during LOCA conditions.
3/4.6.5.1 ICE BED The OPERABILITY of the ice bed ensures that the required ice inventory will 1) be distributed evenly through the containment bays, 2) contain suffi-cient boren to preclude dilution of the containment sump following the LOCA and
- 3) contain sufficient heat removal capability to condense the reactor system i
volume released during a LOCA.
These conditions are consistent with the assumptions used in the accident analyses.
l The minimum weight figure of 1071 pounds of ice per basket contains a 15%
l conservative allowance for ice loss through sublimation which is a factor of 15 higher than assumed for the ice condenser design. The minimum weight figure of 2,082,024 pounds of ice also contains an additional 1% conservative allowance l
to account for systematic error in weighing instruments.
In the SEQUOYAH - UNIT 2 B 3/4 6-4 Amendment No. 21, 118, 135, 215