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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
-. - _ = - .- - -- . . . - ..
Con'monweahh Ediwn Company 1400 Opus Place Downers Gros c. II. M5 t 5 5'01 June 17,1997 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Document Control Desk 4
Subject:
Byron Nuclear Power Station, Units 1 & 2 Facility Operating Licenses NPF-37 & NPF-66 NRC Docket Numbers: 50-454 and 50-455 Braidwood Nuclear Power Station, Units 1 & 2 Facility Operating Licenses NPF-72 & NPF-77 NRC Docket Numbers: 50-456 and 50-457
" Containment Vessel StructuralIntegrity"
) Pursuant to Title 10, Code of Federal Regulations, Part 50, Section 90 (10 CFR 50.90),
Commonwealth Edison Company (Comed) proposes to amend Appendix A, Technical Specifications, for Facility Operating Licenses NPF-37 and NPF-66 for Byron Nuclear Power Station,
. Units 1 & 2 and Facility Operating Licenses NPF-72 and NPF-77 for Braidwood Nuclear Power i Station, Units I and 2. )
l Comed proposes to revise the Technical Specifications Sections 3/4.6.1.6,4.6.1.2, 6.8.4 and 6.9.1.11, to support the new requirements published in 10CFR50.55a which requires utilities to 4 update their existing Containment Vessel Structural Integrity Programs to meet the requirements found in Subsection IWL of the 1992 Edition,1992 Addenda of ASME Section XI and five additional modifications found in 10CFR50.55a(b)(2)(ix). Additionally, this technical i specification amendment incorporates Regulatory Guide 1.35.1,1990, " Determining Prestressing Forces for Inspection of Prestressed Concrete Containment."
This package consists of the following:
Attachment A Description and Safety Analysis of Proposed Changes to
)
Appendix A Attachment B-1 Marked Up Pages for Proposed Changes to Appendix A for Byron Station Attachment B-la Marked Up Pages for Proposed Changes to Proposed Improved ik Technical Specification for Byron Station. . b,g 1
- Attachment B-2 Marked Up Pages for Proposed Changes to Appendix A for Braidwood Station 9706240134 970617 'il@llli PDR ADOCK 05000454 i litililli
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i NRC Document Control Desk -2 June 17,1997 Attachment B-2a Marked Up Pages for Proposed Changes to Proposed Improved Technical Specification for Braidwood Station Attachment C Evaluation of No Significant Hazards Consideration for Proposed Changes to l Appendix A Attachment D Environmental Assessment for Proposed Changes to Appendix A The proposed changes in this license amendment have been reviewed and approved by both On-Site and Off-Site review in accordance with Comed procedures.
Comed is notifying the State ofIllinois of our application for this license amendment request by
, transmitting a copy of this letter and its attachment to the designated State Official.
4
- This amendment request is required for the next scheduled unbonded post-tensioning and
. reinforced concrete inservice examinations. These examinations are scheduled for 1998 at Byron and 2001 at Braidwood. Approval of this change is requested by January 10,1998, to support the scheduled for the next inservice examination at Byron.
4 I aflirm that this transmittal is true and correct to the best of my knowledge, information and
- belief.
Please address any comments or questions regarding this matter to Denise Saccomando, Senior PWR Licensing Administrator at (630) 663-7283.
, Sincerely, :::.:::. :::: : ::. : :
h,:::: OFFICIAL SEAL 3
i
, [/ G JACQUELINE T EVANS $
h NOTARY PU6UC, STATE of ILUN048 John B. Hosmer 4 MYCO '
9:::::,MMISSION EXPIRES:12/15/97 Engineering Vice President :::::::::::: _
Signed before me on this / day of /4 ,1997 by h04gs F
L[ fM M Notary Public
) Attachments cc: A. B. Beach, Regional Administrator - Rlll G. F. Dick, Jr., Byron /Braidwood Project Manager - NRR
- S. D. Burgess, Senior Resident Inspector - Byron C. J. Phillips, Senior Resident Inspector - Braidwood
- l. Oflice of Nuclear Safety - IDNS l
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i ATTACHMENT A DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF FACILITY OPERATING LICENSES NPF-37, NPF-66, NPF-72, AND NPF-77 A. DESCRIPTION OF Tile PROPOSED CIIANGE Commonwealth Edison (Comed) proposes to revise the Technical Specifications (TS) for the Concrete Containment Tendon surveillances. Comed will add a surveillance program to comply with Title 10 of the Code of Federal Regulations (10 CFR) Section 50.55a(b)(2)(vi) and Section 50.55a(b)(2)(ix). Byron Nuclear Power Station Units 1 & 2 (Byron) and Braidwood Nuclear Power Station Units 1 & 2 (Braidwood) propose to revise the following TSs:
TS 3/4.6.1.6, " Containment Vessel Stnictural Integrity," and associated Bases will be revised to delete current surveillance detail; TS Surveillance Requirement (TSSR) 4.6.1.2 will be revised to incorporate the requirements of TSSR 4.6.1.6.3.
TS 6.8.4.g will be added to ensure a program is provided that demonstrates containment vessel structuralintegrity; and TS 6.9.1.11 will be added to ensure a report is provided to the NRC within 30 days following the detection of any abnonnal degradation of the containment structure.
The CFR requires that the containment vessel structural integrity be determined in accordance with the requirements of ASME Section XI,1992 Edition,1992 Addenda, Subsection IWL,
" Requirements for Class CC Concrete Components of Light-Water Cooled Power Plants," and the five modifications presented in 10 CFR 50.55a(b)(2)(ix), " Examination of concrete containments."
The proposed changes are discussed in detail in Section D of this attachment. The affected current TS pages are shown in Attachments B-1 and B-2 with the changes noted. The affected Improved TS (ITS) pages are shown in Attachments B-1a and B-2a with the changes noted.
B. DESCRIFTION AND BASES OF TIIE CURRENT REQUIREMENTS The current TS Limiting Condition for Operation (LCO) 3.6.1.6 requires the containment to be operable per the surveillance requirements. TSSRs 4.6.1.6.1 and 4.6.1.6.2 provide the methods for scheduling, inspecting and testing the tendons; testing individual wire strands taken from the specified tendons; inspecting and measuring the amount of grease coverage for the tendons; and inspecting the end anchorages and adjacent surfaces. TSSR 4.6.1.6.3 supports the inspections of 3
the containment vessel surfaces prior to a Type A containment leakage rate test. A footnote to LCO 3.6.1.6 permits a one-time exception to the requirements of TSSR 4.6.1.6.1 for Unit I to allow the sheathing filler grease voids to be in excess of 5% of the net duct volume for up to 35 l tendons until the end of the steam generator rer;acement outage at each Station.
l The current bases for the inspection and structural integrity assessment for the performance of the Containment Vessel Examination is provided in proposed Revision 3 to Regulatory Guide 1.35,
" Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures,"
l April 1979. The current bases for the determination of prestressing forces for the performance of l tendon lift-offs are provided in proposed Regulatory Guide 1.35.1," Determining Prestressing Forces for Inspection of Prestressed Concrete Containments," April 1979.
Proposed Regulatory Guide 1.35.1 provides guidance for determining the current expected prestressing forces in the tendons selected for surveillance activities.
C. NEED FOR REVISION OF THE REQUIREMENTS The revision of the current requirement is required to meet a recent revision 10 CFR 50.55a.
Specifically,10 CFR 50.55a(b)(2)(vi) includes compliance Subsection IWL and 10 CFR 10.55a(b)(2)(ix) describes five modifications to IWL. The revision took effect on September 9,1996. 10 CFR 50.55a(g)(6)(ii)(B)(4) allows the post-tensioning system surveillance requirements to be satisfied by the existing post-tensioning program accepted by the NRC prior to September 9,1996. However, the statements presented in the Federal Register discussion of
! 10 CFR 50.55a(g)(6)(ii)(B)(4) are not clear as to whether inspections in accordance with proposed Revision 3 to Regulatory Guide 1.35 are acceptable. To incorporate the requirements of 10 CFR 50.55a(b)(2)(vi) and the five modifications in 10 CFR 50.55a(b)(2)(ix), a program is added to the Administrative Conti : s Section of the TS. The details of the structural integrity surveillance requirements are relocated to this owner-controlled program. This approach is consistent with NUREG 1431, " Standard Technical Specifications for Westinghouse Plants,"
Revision 1.
D. DESCRIPTION OF Tile REVISED REQUIREMENTS Revision to Current TS (Attachments B-1 and B-2)
The following changes are proposed to incorporate the CFR requirements:
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+ TSSR 4.6.1.2 will be revised to incorporate the requirements of TSSR 4.6.1.6.3. This l TSSR provides requirements for inspection of containment vessel surfaces.
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e LCO 3.6.1.6 will be revised to replace the specific requirements that describe containment operability with a statement that the containment is required to be operable. The provision noted in the footnote to LCO 3.6.1.6 will be relocated to TS 6.8.4.g. Action statements for LCO 3.6.1.6 will be revised to permit one hour to restore containment operability or require a plant shutdown.
- The requirements of TSSRs 4.6.1.6.1 and 4.6.1.6.2 will be relocated to the Containment Vessel Structural Integrity Program.
. TSSR 4.6.1.6.3 will be relocated to TS 3/4.6.1.2.
. Bases 3/4.6.1.6 will be revised to replace the existing program compliance recommendations of proposed Revision 3 to Regulatory Guide 1.35, " Inservice Inspection of Ungrouted Tendons in Prestressed Concrete Containment Structures," April 1979, with the requirements of 10 CFR 50.55a(b)(2)(vi) and 10 CFR 50.55a(b)(2)(ix). Additionally, the Bases will be revised to replace the reference to proposed Regulatory Guide 1.35.1, April 1979, with a reference to the issued Regulatory Guide 1.35.1, July 1990.
- TS 6.8.4.g will be added to define the containment vessel structural integrity program.
The exception noted in the footnote to LCO 3.6.1.6 is included as an additional provision.
- TS 6.9.1.1 I will be added to provide a report to the NRC within 30 days ofdetecting abnormal degradation of the containment structure found during inspection.
Revision to ITS (Attnchments B-1n nnd B-2n)
Comed submitted an application for conversion to the ITS in a letter from G. Stanley and K. Graesser to the NRC dated December 13,1996. In order to incorporate license amendments for requests submitted afler December 13,1996 into the ITS, markups have been provided on the Proposed ITS in addition to the current TS. The requested changes to the proposed ITS are as follows:
. SR 3.6.1.2 will be revised to reflect the program name change to " Containment Vessel Structural Integrity Program."
. SR 3.6.1.2 Bases section will be revised to delete proposed Revision 3 to Regulatory Guide 1.35, April 1979, and proposed Regulatory Guide 1.35.1, April 1979. The requirements of 10 CFR 50.55a(b)(2)(vi) and 10 CFR 50.55a(b)(2)(ix), and the recommendations of Regulatory Guide 1.35.1, July 1990, will be added. The program name change and provision for tendon grease removal are also reflected.
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Section 5.5.6 will be revised to delete references to proposed Revision 3 to Regulatory l Guide 1.35, April 1979, and proposed Regulatory Guide 1.35.1, April 1979. These are l replaced by the requirements of 10 CFR 50.55a(b)(2)(vi) and 10 CFR 50.55a(b)(2)(ix), l and the recommendations of Regulatory Guide 1.35.1, July 1990.
- Section i6.8 will be revised to reflect the program name change.
E. BASES FOR THE REVISED REQUIREMENTS I 10 CFR 50.55a(b)(2) took effect on September 9,1996, resulting in the need to revise the current TS. Byron and Braidwood detennined that the existing programs did not perform the additional exams required by the CFRs. Therefore, Byron and Braidwood are revising the current TS requirements.
In addition, the NRC approved a provision for Unit 1 tendon grease coverage to facilitate removal l
of up to 35 containment tendons in advance of the each station's steam generator replacement '
outage. The NRC documented its acceptance of the provision in an SER dated May 6,1997 for Amendnwnts 89 (Byron) and 81 (Braidwood). The provision is maintained as part of the prograra described in TS 6.8.4.g. This provision is only applicable until the end of the respective steam generator replacement outages for Byron Unit I and Braidwood Unit 1.
Byron and Braidwood are adding a Containment Vessel Structural Integrity Program to meet the requirements of the CFR. Additionally, Byron and Braidwood are revising the recommendations contained in this program from those described in proposed Regulatory Guide 1.35.1 (1979) to i I
those described in the issued Regulatory Guide 1.35.1 (1990). There are no significant changes from the proposed regulatory guide to the issued regulatory guide. ;
F. IMPACT OF TIIE PROPOSED CllANGES The program currently in place to meet the current TSSRs will not be significantly impacted by incorporation of the CFR requirements. However, additional requirements will be added to the overall program as a result ofincorporating 10 CFR 50.55a(b)(2), including, but not limited to, the following:
= Visual inspection of grease caps that are accessible,
- Evaluation of consecutive surveillances of prestressing forces for the same tendon or a group of tendons,
- Examination of ab concrete surfaces,
- Qualifications for the visual examination of the personnel performing concrete exams, 6
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e Use of a registered professional engineer to evaluate the results following the concrete l examinations, and l
- Evaluation of the acceptability ofinaccessible areas when conditions could indicate the presence of degradation.
Currently, there is an outstanding application for amendment to TS 3/4.6.1 and associated Bases, submitted to the NRC on January 30,1997, that requests an increase in the peak containment pressure (Pa). Since this request has not been approved, the markups in Attachments B-1 and B-2 are done on current TS pages that have not incorporated these changes.
There is also an outstanding application for amendment, submitted to the NRC on May 19,1997, ,
that relocates pressure and temperature limits to a Pressure-Temperature Limits Report (PTLR). l This afl'ects page 6-23 of the current TS by adding the PTLR as item 6.9.1.I1. Since this request has not been approved, the markups in Attachments B-1 and B-2 are done on current TS pages that have not incorporated this change. Therefore, the Containment Vessel Structural Integrity l Report is added to the current TS as item 6.9.1.11. Whichever application for amendment is l approved first, will have its associated report designated 6.9.1.11 with the subsequent amendment report designated 6.9.1.12.
G. SCIIEDULE REQUIREMENTS These changes are required for the next scheduled unbonded post-tensioning and reinforced concrete inservice examinations. These examinations are scheduled for 1998 at Byron and 2001 at Braidwood. Approval of this change is requested by January 10,1998 to support the schedule for the next inservice examination at Byron.
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