|
---|
Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20210J1711999-07-30030 July 1999 Application for Amends to Licenses NPF-72 & NPF-77,proposing Temporary Changes to TS Re Upper Temperature Limit for Ultimate Heat Sink ML20209B7301999-06-30030 June 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,providing Correction to LCO Associated with TS Section 3.8.5, DC Sources - Shutdown & Deleting Various References to At&T Batteries in Braidwood TS Section 3.8 ML20204H9661999-03-23023 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TSs to Support Installation of New Boral high-density SFP Storage racks.Non-proprietary & Proprietary Info Encl.Proprietary Info Withheld.Per 10CFR2.790 ML20204H4211999-03-22022 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20198N3351998-12-29029 December 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Twelve RTS & ESFAS Allowable Values Contained in ITS Table 3.3.1-1 & Table 3.3.2-1 ML20196B3941998-11-25025 November 1998 Application for Amends to Licenses NPF-72 & NPF-77, Facilitating Replacement of 125 Vdc At&T Batteries with New 125 Vdc C&D Batteries While in Mode 1-4 ML20195J4101998-11-19019 November 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising App C,Addl License Conditions,By Deleting & Adding License Conditions as Stated.Marked Up App C Pages, Encl ML20155H9941998-10-30030 October 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Design Features Description Contained in Section 5.6.2 ML20248C5301998-05-29029 May 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Bases Section 3/4.4.4, Relief Valves to Credit Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS ML20217E1771998-03-24024 March 1998 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Surveillance Sections & Bases to Allow Util to Defer 10CFR50,App J Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20198L7981998-01-14014 January 1998 Application for Amends to Licenses NPF-72 & NPF-77, Revising TS to Reduce Dose Equivalent I-131 Activity from Requested 0.1 Microcuries/Gram to 0.05 Based on Revised Total end-of-cycle 7 Projected Leak Rate Value ML20198L8701998-01-14014 January 1998 Application for Amends to Licenses NPF-72 & NPF-77, Respectively.Proposed Amends Revise TS Section 3/4.8.2 & Bases,To Allow Replacement of 125 Volt Dc At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries ML20198C2961997-12-30030 December 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.7.1.3, Condensate Storage Tank & Associated Bases for Plants to Raise Min Allowable CST Level ML20199A4651997-11-0707 November 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively.Amends Would Revise TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.b & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20198J9301997-10-16016 October 1997 Application for Amend to License NPF-37,requesting Exemption from Requirements of 10CFR70.24(a), Criticality Accident Requirements. Request Is Being Docketed to Reflect Units 1 & 2 So That Amend Numbers Remain Identical ML20202F4481997-10-10010 October 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Convert Byron & Braidwood Current Tech Specs to Byron & Braidwood Improved Tech Specs ML20211D9341997-09-24024 September 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Allowable Time Interval for Performing Turbine Throttle valve.Non-proprietary & Proprietary Trs,Encl.Proprietary Info Withheld ML20216G8341997-09-0808 September 1997 Application for Amend to TS 4.5.2.b & Associated Bases to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,to Bring Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20216F1141997-09-0202 September 1997 Application for Amends to Licenses NPF-72 & NPF-77,revising TS Section 3.4.8, Specific Activity. Rev 0 to Calculation BRW-97-0798-M & Rev 3 to Calculation 95-011 Encl ML20148P7041997-06-30030 June 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3041997-06-24024 June 1997 Suppl to 970524 Application for Amends to Licenses NPF-66 & NPF-77,revising TS 4.5.2.b Re Venting of ECCS Pump Casings & Discharge Piping High Points Outside of Containment.Proposed Changes to Bases Revised to Delete Ref to Pressure ML20141B7551997-06-17017 June 1997 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Sections 3/4.6.1.6,4.6.1.2,6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a ML20148J3031997-06-0909 June 1997 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,reflecting Latest Rev of Waste Gas Decay Accident Dose Calculation ML20140D0011997-05-31031 May 1997 Suppl to 970523 Application for Exigent Amend to License NPF-37,revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8961997-05-24024 May 1997 Application for Exigent Amends to Licenses NPF-37,NPF-66 & NPF-77,revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K8891997-05-23023 May 1997 Suppl to 970523 Application for Emergency Amend to License NPF-72,revising TS Surveillance Requirement 4.5.2.b.1 Re ECCS Pump Casings & Discharge Piping High Points Outside Containment.Changes Proposed Limit to End of Cycle 7 ML20148D6721997-05-23023 May 1997 Application for Emergency Amend to License NPF-72,revising Surveillance Requirement 4.5.2.b.1 for Unit as It Relates to Requirement to Vent ECCS Pump Casings & Discharge Piping High Points Outside Containment ML20141J9781997-05-21021 May 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Allow Licensee Control of RCS Pressure & Temp Limits for Heatup,Cooldown,Low Temp Operation & Hydrostatic Testing ML20148B6071997-05-0606 May 1997 Application for Amends to TS of Licenses NPF-37 & NPF-66, Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0401997-04-25025 April 1997 Suppl to 970130 Application for Amends to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,revising TS for Containment & RCS Vol.Encl marked-up Improved TS Pages Were Not Included in Original Submittal ML20137S5241997-04-0707 April 1997 Application for Amends to Licenses NPF-37 & NPF-66,revising TS 3/4.8.2 to Allow Replacement of 125 Volt Dc Gould Batteries W/New C&D Charter Power Systems Inc Batteries ML20137N9801997-03-24024 March 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,removing Values of cycle-specific Core Operating Limits from TS & Relocating Values to Operating Limit Rept ML20137C5991997-03-14014 March 1997 Application for Amends to Licenses NPF-37 & NPF-66,reducing Allowable Unit 1 RCS Dose Equivalent I-131 from 0.35 Uci/ Gram to 0.20 Uci/Gram for Remainder of Cycle 8 ML20137C7911997-03-14014 March 1997 Application for Amends to Licenses NPF-37 & NPF-66,deleting 12 License Conditions from Unit 1 Operating License & Two License Conditions from Unit 2 Operating License ML20135E6791997-02-28028 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,replacing Original Westinghouse D4 SG at Byron & Braidwood W/B&W International SGs ML20135B5571997-02-24024 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,from Current TS to Improved TS Consistent w/NUREG-1431,Rev 1, STS - W Plants, Dtd Apr 1995 ML20134N8381997-02-18018 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting Rev to Support Steam Generator Replacement ML20134F3751997-01-31031 January 1997 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Bases 3.4.8 to Reduce Allowable Reactor Coolant Sys Dose Equivalent I-131 from 0.35 Uci/G to 0.20 Uci for Remainder of Cycle 8 ML20134E8451997-01-30030 January 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Revised TS 1.0, Definitions, 3/4.6.1, Primary Containment & Associated Bases & 5.4.2, Reactor Coolant Sys Volume, for Bs & Bs to Support SG Replacement ML20134D0321997-01-20020 January 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3.6.3 Containment Isolation Valves for Byron & Braidwood Unit 1 to Support Replacement of Original W Model D4 SGs W/Babcock & Wilcox Intl SGs ML20133B5851996-12-13013 December 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Conversion to Improved Standard TSs ML20134N7661996-11-0505 November 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.9.11,5.6.1.1 & 6.9.1.10 to Allow Util to Take Credit for Soluble Boron in Spent Fuel Pool Water in Maintaining Acceptable Margin of Subcriticality ML20132A0241996-11-0404 November 1996 Application for Amends to Licenses NPF-37 & NPF-72,revising TS 3.6.1.6 to Allow one-time Exemption to Requirements of SR 4.6.1.6.1.e.1 ML20117K3141996-08-30030 August 1996 Application for Amends to Licenses NPF-72 & NPF-77,modifying App A,Ts 3/4.4.5 by Adding Footnote Specifying Repair Criteria for Top of Tube Sheet Indications If Found as Part of Reviewing Previous Unit 1 Oct 1995 EC SG Data ML20117D1451996-08-23023 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Rev to Appendix a TS 3/4.7.7, Non-Accessible Area Exhaust Filter Plenum Ventilation Sys ML20117J0141996-08-19019 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,renewing 3.0 Volt Bobbin Coil Probe,Sg TSP Interim Plugging Criteria Limit for Outside Diameter Stress Corrosion Cracking ML20116F0791996-08-0202 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,eliminating Corrosion Testing Requirement for SG Tube Sleeving ML20108E7791996-04-29029 April 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3/4.7.1, Turbine Cycle Safety Valves & Associated Bases ML20100L2271996-02-27027 February 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,implementing 10CFR50,App J,Option B That Allows Use of Performance Based Surveillance Frequencies for Type A,B & C Tests Rather than Predetermined Intervals ML20100H8841996-02-21021 February 1996 Submits Suppl Info Re Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,proposing to Revise Ten of Line Item TS Improvements Recommended by GL 93-05 1999-07-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20210J1711999-07-30030 July 1999 Application for Amends to Licenses NPF-72 & NPF-77,proposing Temporary Changes to TS Re Upper Temperature Limit for Ultimate Heat Sink ML20209B7301999-06-30030 June 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,providing Correction to LCO Associated with TS Section 3.8.5, DC Sources - Shutdown & Deleting Various References to At&T Batteries in Braidwood TS Section 3.8 ML20204H9661999-03-23023 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TSs to Support Installation of New Boral high-density SFP Storage racks.Non-proprietary & Proprietary Info Encl.Proprietary Info Withheld.Per 10CFR2.790 ML20204H4211999-03-22022 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20198N3351998-12-29029 December 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Twelve RTS & ESFAS Allowable Values Contained in ITS Table 3.3.1-1 & Table 3.3.2-1 ML20196B3941998-11-25025 November 1998 Application for Amends to Licenses NPF-72 & NPF-77, Facilitating Replacement of 125 Vdc At&T Batteries with New 125 Vdc C&D Batteries While in Mode 1-4 ML20195J4101998-11-19019 November 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising App C,Addl License Conditions,By Deleting & Adding License Conditions as Stated.Marked Up App C Pages, Encl ML20155H9941998-10-30030 October 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Design Features Description Contained in Section 5.6.2 ML20248C5301998-05-29029 May 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Bases Section 3/4.4.4, Relief Valves to Credit Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS ML20217E1771998-03-24024 March 1998 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Surveillance Sections & Bases to Allow Util to Defer 10CFR50,App J Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20198L7981998-01-14014 January 1998 Application for Amends to Licenses NPF-72 & NPF-77, Revising TS to Reduce Dose Equivalent I-131 Activity from Requested 0.1 Microcuries/Gram to 0.05 Based on Revised Total end-of-cycle 7 Projected Leak Rate Value ML20198L8701998-01-14014 January 1998 Application for Amends to Licenses NPF-72 & NPF-77, Respectively.Proposed Amends Revise TS Section 3/4.8.2 & Bases,To Allow Replacement of 125 Volt Dc At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries ML20198C2961997-12-30030 December 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.7.1.3, Condensate Storage Tank & Associated Bases for Plants to Raise Min Allowable CST Level ML20198H7521997-12-29029 December 1997 Errata to Amend 94 & 94 to Licenses NPF-37 & NPF-66, Correcting Typo That Was Inadvertently Introduced on TS Page 5-5 ML20199A4651997-11-0707 November 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively.Amends Would Revise TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.b & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20198J9301997-10-16016 October 1997 Application for Amend to License NPF-37,requesting Exemption from Requirements of 10CFR70.24(a), Criticality Accident Requirements. Request Is Being Docketed to Reflect Units 1 & 2 So That Amend Numbers Remain Identical ML20202F4481997-10-10010 October 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Convert Byron & Braidwood Current Tech Specs to Byron & Braidwood Improved Tech Specs ML20211D9341997-09-24024 September 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Allowable Time Interval for Performing Turbine Throttle valve.Non-proprietary & Proprietary Trs,Encl.Proprietary Info Withheld ML20216G8341997-09-0808 September 1997 Application for Amend to TS 4.5.2.b & Associated Bases to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,to Bring Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20216F1141997-09-0202 September 1997 Application for Amends to Licenses NPF-72 & NPF-77,revising TS Section 3.4.8, Specific Activity. Rev 0 to Calculation BRW-97-0798-M & Rev 3 to Calculation 95-011 Encl ML20148P7041997-06-30030 June 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3041997-06-24024 June 1997 Suppl to 970524 Application for Amends to Licenses NPF-66 & NPF-77,revising TS 4.5.2.b Re Venting of ECCS Pump Casings & Discharge Piping High Points Outside of Containment.Proposed Changes to Bases Revised to Delete Ref to Pressure ML20141B7551997-06-17017 June 1997 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Sections 3/4.6.1.6,4.6.1.2,6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a ML20148J3031997-06-0909 June 1997 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,reflecting Latest Rev of Waste Gas Decay Accident Dose Calculation ML20140D0011997-05-31031 May 1997 Suppl to 970523 Application for Exigent Amend to License NPF-37,revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8961997-05-24024 May 1997 Application for Exigent Amends to Licenses NPF-37,NPF-66 & NPF-77,revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141K8891997-05-23023 May 1997 Suppl to 970523 Application for Emergency Amend to License NPF-72,revising TS Surveillance Requirement 4.5.2.b.1 Re ECCS Pump Casings & Discharge Piping High Points Outside Containment.Changes Proposed Limit to End of Cycle 7 ML20148D6721997-05-23023 May 1997 Application for Emergency Amend to License NPF-72,revising Surveillance Requirement 4.5.2.b.1 for Unit as It Relates to Requirement to Vent ECCS Pump Casings & Discharge Piping High Points Outside Containment ML20141J9781997-05-21021 May 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Allow Licensee Control of RCS Pressure & Temp Limits for Heatup,Cooldown,Low Temp Operation & Hydrostatic Testing ML20148B6071997-05-0606 May 1997 Application for Amends to TS of Licenses NPF-37 & NPF-66, Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0401997-04-25025 April 1997 Suppl to 970130 Application for Amends to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,revising TS for Containment & RCS Vol.Encl marked-up Improved TS Pages Were Not Included in Original Submittal ML20137S5241997-04-0707 April 1997 Application for Amends to Licenses NPF-37 & NPF-66,revising TS 3/4.8.2 to Allow Replacement of 125 Volt Dc Gould Batteries W/New C&D Charter Power Systems Inc Batteries ML20137N9801997-03-24024 March 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,removing Values of cycle-specific Core Operating Limits from TS & Relocating Values to Operating Limit Rept ML20137C5991997-03-14014 March 1997 Application for Amends to Licenses NPF-37 & NPF-66,reducing Allowable Unit 1 RCS Dose Equivalent I-131 from 0.35 Uci/ Gram to 0.20 Uci/Gram for Remainder of Cycle 8 ML20137C7911997-03-14014 March 1997 Application for Amends to Licenses NPF-37 & NPF-66,deleting 12 License Conditions from Unit 1 Operating License & Two License Conditions from Unit 2 Operating License ML20135E6791997-02-28028 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,replacing Original Westinghouse D4 SG at Byron & Braidwood W/B&W International SGs ML20135B5571997-02-24024 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,from Current TS to Improved TS Consistent w/NUREG-1431,Rev 1, STS - W Plants, Dtd Apr 1995 ML20134N8381997-02-18018 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting Rev to Support Steam Generator Replacement ML20134F3751997-01-31031 January 1997 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Bases 3.4.8 to Reduce Allowable Reactor Coolant Sys Dose Equivalent I-131 from 0.35 Uci/G to 0.20 Uci for Remainder of Cycle 8 ML20134E8451997-01-30030 January 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Revised TS 1.0, Definitions, 3/4.6.1, Primary Containment & Associated Bases & 5.4.2, Reactor Coolant Sys Volume, for Bs & Bs to Support SG Replacement ML20134D0321997-01-20020 January 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3.6.3 Containment Isolation Valves for Byron & Braidwood Unit 1 to Support Replacement of Original W Model D4 SGs W/Babcock & Wilcox Intl SGs ML20133B5851996-12-13013 December 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Conversion to Improved Standard TSs ML20134N7661996-11-0505 November 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.9.11,5.6.1.1 & 6.9.1.10 to Allow Util to Take Credit for Soluble Boron in Spent Fuel Pool Water in Maintaining Acceptable Margin of Subcriticality ML20132A0241996-11-0404 November 1996 Application for Amends to Licenses NPF-37 & NPF-72,revising TS 3.6.1.6 to Allow one-time Exemption to Requirements of SR 4.6.1.6.1.e.1 ML20117K3141996-08-30030 August 1996 Application for Amends to Licenses NPF-72 & NPF-77,modifying App A,Ts 3/4.4.5 by Adding Footnote Specifying Repair Criteria for Top of Tube Sheet Indications If Found as Part of Reviewing Previous Unit 1 Oct 1995 EC SG Data ML20117D1451996-08-23023 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Rev to Appendix a TS 3/4.7.7, Non-Accessible Area Exhaust Filter Plenum Ventilation Sys ML20117J0141996-08-19019 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,renewing 3.0 Volt Bobbin Coil Probe,Sg TSP Interim Plugging Criteria Limit for Outside Diameter Stress Corrosion Cracking ML20116F0791996-08-0202 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,eliminating Corrosion Testing Requirement for SG Tube Sleeving ML20108E7791996-04-29029 April 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3/4.7.1, Turbine Cycle Safety Valves & Associated Bases ML20100L2271996-02-27027 February 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,implementing 10CFR50,App J,Option B That Allows Use of Performance Based Surveillance Frequencies for Type A,B & C Tests Rather than Predetermined Intervals 1999-07-30
[Table view] |
Text
. - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
s
- /O Ccmmonw=lth Edi:.cn 1v-h 1400 Opus Place Downers Grove, Ilhnois 60515 March 7,1994 William T. Russell, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk Sub cet:
3 Application for Amendment to Facility Operating Licenses:
Byron Station Units 1 and 2 (NPF-37/66; NRC Docket Nos. 50-454/455)
Braidwood Station Units 1 and 2 (NPF-72/77; NRC Docket Nos. 50-456/457)
" Integrated Containment Leakage Rate Test Requirements"
Dear Mr. Russell:
Pursuant to 10 CFR 50.90, Commonwealth Edison Company (CECO) proposes to amend Appendix A, Technical Specifications of Facility Operating Licenses ,
NPF-37, NPF-66, NPF-72, and NPF-77. The subject amendment request proposes to ,
revise Technical Specification Surveillance Requirement 4.6.1.2, " Containment Leakage" A detailed description of the proposed changes is presented in Attachment 1. The revised Technical Specification pages are contained in Attachment 2. j The proposed changes have been reviewed and approved by the On-site and Off-site Review Committees in accordance with CECO procedures. CECO has reviewed this proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists as documented in Attachment 3. An Environmental Assessment has also been completed and is contained in Attachment 4.
110020 f, ' '
EBR31BBN p
86888b PDR 4
)
1
,. 2
. W. T. Russell 2 March 7,1994 CECO is notifying the State of Illinois of our application for these amendments by transmitting a copy of this letter and the associated attachments to the designated State Official.
Byron Unit 1 is scheduled for a refueling outage beginning September 10,1994. i Preparation for an integrated containment leak rate test, should one be required, would have to start no later than June 13,1994, therefore, CECO respectfully requests that .
the Staff review and approve the amendment by June 13,1994.
- To the best of my knowledge and belief, the statements contained in this document '
are true and correct, in some respects these statements are not based on my personal knowledge, but on information furnished by other CECO employees, '
contractor employees, and/or consultants. Such information has been reviewed in accordance with company practice, and I believe it to be reliable.
Please address any comments or questions regarding this matter to this office.
^
Respectfully, fl bbb l MARY JO bhAbYACK
,S l NOT AHY PUBLIC. STATE OF ILUNOIS ggf 4
$$$$N1?
' Joseph A. Bauer r w % Tc c( M7/9/ Nuclear Licensing Administrator l !. -i i JAB /gp Attachments ,
cc: G. F. Dick, Byron Project Manager - NRR R. R. Assa, Braidwood Project Manager - NRR H. Peterson, SRI - Byron S. G. Dupont, SRI - Braidwood B. Clayton, Branch Chief - Region lil Office of Nuclear Facility Safety - IDNS i
l '
\
PROPOSED LICENSE AMENDMENT l
" INTEGRATED CONTAINMENT LEAKAGE RATE TEST REQUIREMENTS" INDEX ,
l Attachment 1 Detailed Description of Proposed Change Attachment 2 Proposed Changes to Appendix A, Technical Specifications for Facility Operating Licenses NPF-37, NPF-66, NPF-72 and NPF-77 Attachment 3 Evaluation of Significant Hazards Consideration Attachment 4 Environmental Assessment Attachment 5 Byron's Periodic Type A Test Schedule l
l l
ATTACHMENT 1 DETAILED DESCRIPTION OF PROPOSED CHANGE Description of Current Requirements:
. Technical Specification 3.6.1.2 provides the containment leakage rate requirements and surveillance requirements for inspection, inspection frequency, and acceptance criteria. Surveillance Requirement 4.6.1.2 references the criteria specified in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4-1972, (" Leakage Rate Testing of Containment Structures for Nuclear Reactors"). Surveillance Requirement 4.6.1.2.a specifies that three Type A tests, overall integrated containment leakage rate (ILRT), are conducted at 40110 month time intervals. Also,4.6.1.2.a specifies that the third Type A test is to be conducted during the 10-year plant inservice inspection.
Bases for the Current Requirements:
Specification 4.6.1.2 '
Surveillance Requirement 4.6.1.2 specifies that containment leakage testing shall be done in conformance with the requiroments of 10 CFR 50 Appendix J and using the methods and provisions of ANSI 45.4-1972. Appendix J provides testing requirements for pre-operational and periodic verification by tests of the leak-tight integrity of the primary reactor containment, and systems and components which penetrate containment of water-cooled power reactors, ;
and establish acceptance criteria for such tests, l Specification 4.6.1.2.a Appendix J of 10 CFR 50 sets forth requirements for containment leakage !
testing and ensures that a set of three Type A tests be performed at I approximately equal intervals during each 10 year service period. The intent of the established time interval of 40 t 10 months for the performance of the Type A tests in Surveillance Requirement 4.6.1.2.a was to meet this requirement of conducting three (3) approximately equally spaced Type A tests over the 10 year (120 month) service period. The time interval of 40
- 10 months was chosen to allow some scheduling flexibility while still ensuring relatively even spacing between the three tests. ;
i i
i y . _ .,- .
Attachment 1 Page 2 Description of the Need for Amending the Technical Specifications:
Soecification 4.6.1.2 The removal of the reference to ANSI N45.4-1972 is an editorial change only.
Appendix J of 10 CFR 50, Section Ill. A.3, " Test Methods," references ANSI N45.4-1972. Thus, removal of this reference from Surveillance Requirement 4.6.1.2 will not change adherence to the ANSI document, as it is required by 10 CFR 50.
Soecification 4.6.1.2.a Braidwood Units 1 and 2 currently meet the required time intervals established for Type A testing in Surveillance Requirement 4.6.1.2.a. This change is requested for Braidwood to ensure consistency with Byron Station and also to ,
preclude the need for future Technical Specification changes should Appendix J
, of 10 CFR 50 be revised.
Byron Units 1 and 2, in order to meet the 40 10 month Type A test schedule as described in Surveillance Requirement 4.6.1.2.a. will be required to perform back-to-back Type A overall containment integrated leak rate tests. The Type A ;
tests would be required to be performed during refueling outage #6 and again i during refueling outage #7 for each unit (see Attachment 5 for outage schedules '
and performance of Type A tests).
For Byron Unit 1, this schedule would require a third Type A test to be performed on or before 11/15/95, which corresponds to a test during refueling outage B1R06, to prevent exceeding the 50 month maximum time interval from the last Type A test conducted during B1R04, completed 9/15/91. Another Type A test would be required during refueling outage B1R07, scheduled for March of 1996, to satisfy the 10-year ISI requirement. Scheduling a fourth Type A test during refueling outage #7 to meet the ISI requirement would also be less than the 30 month minimum time limit for the surveillance intervals.
This Technical Specification revision allows the third Type A test to be performed during the seventh refueling outage to meet the requirements of performing a third Type A test during the shutdown for the 10-year plant inservice inspection and eliminates the need to perform Type A tests during back-to-back refueling outages. !
1 I
f
--u m , - ce, -- - , , ---, - , - - - . - , - ,
,' .. I Attachment 1 ,
Page 3
]
i For Byron Unit 2, the last Type A test was completed during B2R04 on 9/9/93. 1 The same concern of performing Type A tests during back to back refueling )
outages would apply if the time intervals specified in Appendix J and Surveillance 4.6.1.2.a were to be met.
i For Byron Units 1 and 2, the current 18 month fuel cycle makes maintaining a 40
- 10 month time interval for Type A testing difficult without asking for an ,
extension on the third test to allow performance at fifty-four (54) months to !
coincide with the seventh refueling outage which is the 10-year Inservice Inspection outage. The removal of the required time interval requirement would allow the third Type A test to be performed during the seventh refueling outages for Byron Units 1 and 2 for the 10-year service period and coincide with the 10-year plant inservice Inspection. The third Type A test would be performed no later than April 1,1996 for Byron Unit 1 and April 1,1998 for Byron Unit 2 ;
corresponding the performance of the third Type A test at a time interval of 54 months.
I Description of the Proposed Amendment:
Specification 4.6.1.2 Commonwealth Edison (CECO) proposes an editorial change to the first sentence of Surveillance Requirement 4.6.1.2 after "10 CFR 50" by deleting the words "using the methods and provisions of ANSI N45.4-1972".
I Sp_ecification 4.6.1.2.a CECO also proposes a change to the Byron and Braidwood Technical Specifications by deleting the word "Three" at the beginning of Specification 4.6.1.2.a and deleting the time interval schedule of 40
- 10 months. Type A testing will conform to intervals specified in Appendix J of 10 CFR 50 for the Type A tests, which currently requires three Type A tests at approximately equal intervals with the third test occurring during the 10 year Inservice Inspection. The proposed change will adopt the guidance and wording provided in NUREG 1431, " Standard Technical Specifications for Westinghouse Plants."
l I
u- rmr -c _- _ -. _ - -________----_m_.
.l -
Attachment 1 Page 4 s
impact of Proposed Change Specification 4.6.1.2 The removal of the reference to ANSI N45.4-1972 is an editorial change request. All Type A tests are required to be conducted in accordance with the provisions of the ANSI document as referenced in Section Ill.A.3, " Test Methods", of Appendix J of 10 CFR 50. The removal of the reference does not change the testing method of any of the associated components and penetrations, nor does it affect any assumption or condition in any of the accident analyses.
SpAcification 4.6.1.2.a The proposed change will adopt the guidance and wording provided in NUREG 1431, " Standard Technical Specifications for Westinghouse Plants.'
Future testing intervals will be in accordance with the criteria specified in Appendix J of 10 CFR 50 for the Type A tests.
Braidwood will not be immediately impacted the proposed deletion of the 40
- 10 month periodicity. Braidwood is currently able to meet Technical Specification required intervals. This change, for Braidwood, will ensure consistency with Byron and minimize any future schedule conflicts which might occur due to a specified testing interval.
Byron will be allowed, via this proposed amendment, to extend its third Type A test to 54 months. This extension is based on results of the previous Type A leak tests which have shown that the overall leakage from Byron Unit 1 and Unit 2 containment buildings were at low levels. The test results for the latest Unit 1 Type A test was measured at 0.0175 weight percent per day. The associated 95% upper confidence level (UCL) was calculated to be 0.0184 weight percent per day. The test results for the latest Unit 2 Type A test was measured at 0.0376 weight percent per day. The associated 95% UCL was calculated to be 0.0666 weight percent per day. The Unit 2 95% UCL is relatively high with respect to the measured leakage rate due to the Bechtel Nuclear Topical Report (BN-TOP) mass-point process used. The overall containment leakage rate has consistently remained well below acceptable levels for Byron Station Type A tests of 0.075 weight percent per day.
Elimination of the specified time intervals for the Type A testing would allow ;
extending the time interval of the third Type A test by four (4) months beyond l the existing maximum 50 month interval. The extension would allow l
I i
Attachment 1 Page 5 performance of the Type A test to coincide with the seventh refueling outage, the 10 year Inservice Inspection, and meet the requirements of Appendix J of 10 CFR 50.
For Byron, the present test performance margins, coupled with the present Type B & C test program for monitoring and repairing individual leakage components provide justification for the proposed change which extends the third Type A test to 54 months. Type B and C tests have been completed satisfactorily at the required frequency and are scheduled for completion during refueling outage number seven. Demonstrated operability of the associated components and penetrations provides added assurance that the overall containment integrated leakage rates iemain satisfactory. No significant leakage trends have been identified which threaten the overall containment leakage specifications. There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite due to the allowance of the performance of the Type A test to coincide with the seventh refueling outage and the 10 year Inservice Inspection.
The proposed Technical Specifications change does not involve any change to the configuration or method of operation of any plant equipment that is used to mitigate the consequences of an accident, nor does it affect any assumption or condition in any of the accident analyses.
Schedule Requirements: l Byron Unit 1 is scheduled for a refueling outage beginning September 10,1994.
Preparation for an integrated containment leak rate test, should one be <
required, would have to start no later than June 13,1994, therefore, CECO respectfully requests that the Staff review and approve the amendment by June 13,1994.
,-----v. ._ , -. , _ - -