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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
MONTHYEARML20217N3631999-10-13013 October 1999 Amends 111,111,104 & 104 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Requirements Related to cross- Tie DC Power Buses Between Units & Removing Refs to At&T Batteries Which Have Been Replaced at Braidwood Station ML20212A6801999-09-0909 September 1999 Corrected Tech Spec Pages 4 to Amends 110 & 110 to Licenses NPF-37 & NPF-66,correcting License Conditions 2.C(17) & 2.C(6) ML20212A8121999-09-0808 September 1999 Amends 103 & 103 to Licenses NPF-72 & NPF-77,respectively, Changing Max Allowable Temp of UHS in TSs from 98 Degrees F to 100 Degrees F ML20211A8071999-08-10010 August 1999 Amends 110 & 110 to Licenses NPF-37 & NPF-66,respectively, Deleting License Conditions Which Have Been Satisfied, Revising Others to Delete Parts No Longer Applicable or to Revise References & Making Editorial Changes ML20210J1711999-07-30030 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 ML20207F1181999-06-0202 June 1999 Amend 102 to Licenses NPF-72 & NPF-77,revising TS 3.9.3 Re Use of Gamma-Metrics post-accident Source Range Neutron Flux Monitors as Alternative to Westinghouse Source Range Neutron Flux Monitors During Mode 6 Operations (Refueling) ML20206G5961999-05-0303 May 1999 Amends 108,108,101 & 101 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Requirements for Spent Fuel Pool Inadvertent Draindown Elevation ML20206B5451999-04-23023 April 1999 Amends 107 & 107 to Licenses NPF-37 & NPF-66,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & ESFAS ML20206B6841999-04-23023 April 1999 Amends 100 & 100 to Licenses NFP-72 & NPF-77,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & Efsas ML20205D6511999-03-26026 March 1999 Amends 99 to Licenses NPF-72 & NPF-77,respectively,changing TS to Support Online Replacement of Vital Batteries 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 ML20195D5081998-11-0404 November 1998 Errata to Amends 96 & 96 to Licenses NPF-72 & NPF-77, Respectively,Correcting TS Page 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 ML20154P1571998-10-15015 October 1998 Amends 97 & 97 to Licenses NPF-72 & NPF-77,respectively, Revising TS Re non-accessible Area Exhaust Filter Plenum Ventilation Sys to Reflect Design Lineup ML20151T2001998-09-0303 September 1998 Amends 95 & 95 to Licenses NPF-72 & NPF-77,respectively, Changing TS Limits on RCS Dei ML20237D4471998-08-18018 August 1998 Amends 94 & 94 to Licenses NPF-72 & NPF-77,respectively, Revising TS to Support Replacement of 125 Volt Direct Current At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries 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 ML20248F4521998-05-26026 May 1998 Amends 93 & 93 to Licenses NPF-72 & NPF-77,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Governor Valves from Monthly to Quarterly ML20248E0221998-05-26026 May 1998 Amends 103 & 103 to Licenses NPF-37 & NPF-66,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Govern Valves from Monthly to Quarterly ML20216C1161998-05-0808 May 1998 Amends 102 & 102 to Licenses NPF-37 & NPF-66,respectively, Deferring Next Scheduled Type a Containment Integrated Leak Rate Test for Plant,Unit 2,until Next Refueling Outage in 1999 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 ML20203B7231998-02-0303 February 1998 Amends 92 & 92 to Licenses NPF-72 & NPF-77,respectively, Revise TS to Reflect Forthcoming Replacement of Original Steam Generators ML20203A2751998-02-0303 February 1998 Amends 101 & 101 to Licenses NPF-37 & NPF-66,respectively, Reflect Forthcoming Replacement of Original Steam Generators ML20199E6871998-01-29029 January 1998 Amends 99,99,90 & 90 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TSs to Update Containment Vessel Structural Integrity to Meet Provisions of Recent Rev to 10CFR50.55a ML20199K4681998-01-23023 January 1998 Amends 89 & 89 to Licenses NPF-72 & NPF-77,respectively, Relocating RCS Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & Associated LTOP Sys Setpoint Curves ML20199J0281998-01-23023 January 1998 Amends 98 & 98 to Licenses NPF-37 & NPF-66,respectively, Relocating,Rcs Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & LTOP Sys Setpoint Curves ML20199F3631998-01-22022 January 1998 Amends 97 & 97 to Licenses NPF-37 & NPF-66,respectively. Amends Revise TS & Associated Bases Re Primary Containment Pressure & Reactor Coolant Sys Volume ML20199H7861998-01-22022 January 1998 Amends 88 & 88 to Licenses NPF-72 & NPF-77,respectively, Revising TS & Associated Bases Re Primary Containment Pressure & RCS Vol ML20199D2441998-01-15015 January 1998 Amends 87 & 87 to Licenses NPF-72 & NPF-77,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement ML20199C1651998-01-15015 January 1998 Amends 96 & 96 to Licenses NPF-37 & NPF-66,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement at Plant 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 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 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 ML20198B5691997-12-12012 December 1997 Amends 95 & 95 to Licenses NPF-37 & NPF-66,respectively, Changing TS 3/4.7.5, UHS & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20203D3581997-12-0404 December 1997 Amends 94 & 94 to Licenses NPF-37 & NPF-66,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20203F6511997-12-0404 December 1997 Amends 86 & 86 to Licenses NPF-72 & NPF-77,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20202E5711997-11-25025 November 1997 Amends 93 & 93 to Licenses NPF-37 & NPF-66,respectively, Revising TS to Permit Installation & Use of C&D Charter Power Sys,Inc,Batteries 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 ML20210K7021997-08-13013 August 1997 Amend 91 to License NPF-66,revising TS 4.5.2.b.1 to Clarify That Venting Only Required on ECCS Subsystems That Are Idle or Stagnant 1999-09-09
[Table view] |
Text
,
Commonwacith Edison
- 2. ___
1400 Opus Place v ~
Downers Grove filinois 60515 August 31,1993 Dr. Thomac E. Murley, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk
Subject:
Application for Amendment to Facility Operating
-l Licenses-Control Room Ventilation System Chiller:
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
Reference:
NUREG 1431, Standard Technical Specifications for Westinghouse.
7 Plants l
Dear Dr. Murley:
Pursuant to 10 CFR50.90, Commonwealth Edison Company (CECO) proposes to amend Section 3.7.6 of Technical Specifications of Facility Operating Licenses NPF-37,NPF-66, NPF-72, and NPF-77. The proposed amendment request a revision to the Limiting Condition for Operation for the Control Room Ventilation System.
The amendment request is subdivided as follows:
Attachment A:
Description and Safety Analysis of Proposed Changes t
Attachment B:
Proposed Revision to the Technical Specifications for Byron and Braidwood Stations Attachment C:
Evaluation of Significant Hazards Considerations -
i 0
$i Attachment D:
Environmental Assessment 9309070216 930831 0'
^oock 05o004s4
!?i PDR y
k:nla:bw vechillir:1
i I
The proposed changes have been reviewed and approved by the On-site and Off-j 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.
1 CECO is notifying the State ofIllinois of our application for these amendments by transmitting a copy of this letter and the associated attachments to the designated State Official.
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 i
on my personal knowledge, but on information furnished by other CECO I
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 further comments or questions regarding this matter to this office.
l c e y of
/
D ate of i Sincerely, ww w,
~
I
/
/
Notary Pub!h_. _ _ _ V_/
f &
yu N.
Denise M. Saccomando
' uclear Licensing Administrator N
OFFICI AL SE AL ~ $
SANDR/*C.LARA scum Pusut. smE or au'cy p covwSS!ON EXPIRES 0/2!"9;' <
m e: m "
Attachments cc:
J. B. Hickman, Byron Project Manager - NRR R. R. Assa, Braidwood Project Manager - NRR IL Peterson, Senior Resident Inspector - Byron S. G. Dupont, Senior Resident Inspector - Braidwood B. Clayton, Branch Chief-Region III Office of Nuclear Facility Safety - IDNS 1
i k:nla:bw:vechillit:2
i ATTACHMENT A Description and Safety of Proposed Changes Description of the Proposed Changes The proposed amendment would add an ACTION that would allow 30 days to restore one train of VC that is inoperable only due to an inoperabic chiller unit.
If a train of VC becomes inoperable for other reasons, the AOT will remain seven days.
The change would also add an option to Action a in Modes 5 and 6 to allow cessation of CORE ALTERATIONS, positive reactivity additions, and movement of irradiated fuel instead of placing the operable train of VC in makeup mode. Also, the change adds a restriction to Action b to suspend movement ofirradiate.1 fuel if I
both trains of VC are inoperable in Modes 5 and 6. In addition, for consiszency with the wording in Action a, the word " changes" was replaced by the word
" additions."
Description and Bases of the Current Requirement Technical Specification 3.7.6 requires that two independent trains of Control Room Ventilation (VC) be operable in all modes. During operation in Modes I through 4, when one train of VC is inoperable, the Action statement allows seven days to restore the train to operable status before requiring that both nuclear units be in Hot Standby in six hours and Cold Shutdown within 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
If one train of VC becomes inoperable in Modes 5 or 6, the Action statement i
allows seven days to restoie the inoperable train to operable status prior to requiring that the remaining operable train be placed in makeup mode.
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The operability of VC ensures that the ambient air temperature does not exceed the maximum allowable air temperature for equipment and instrumentation in the control room. In addition, VC must be capable of maintaining the control room habitable for operating personnel during and following all credible accident scenarios.
Operation of the VC system must limit the radiation exposure to personnel in the control room to less than 5 rem whole body in accordance with 10CFR50 Appendix A, General Design Criteria 19. The system is designed such that either of two independent one-hundred percent capacity trains can provide these functions.
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Description and Bases of the Requested Revision The requested amendment retains the intent and function of the VC system.
No changes are being made to the design or to the assumptions in the design basis analysis. The proposed revision to the Action statement assures that the inoperable VC chiller unit will be restored within 30 days. The 30 day completion time is based on the low probability of an event requiring control room isolation, the consideration that the remaining train can provide the required protection, and that alternate J
nonsafety related cooling means are available.
The preferred means of alternate cooling involves taking cool air from outside when available and using portable fans. Another alternative would be to cross-tie the Service Building Chiller to the VC system by means of temporary connections. This second option requires several hours of setup time and would be used if cool outside air were not available.
i Although shutdown is required by Technical Specifications, operating with only one chiller is not a functionally degraded condition. In fact, the VC system is designed such that each chiller unit is capable of handling all normal and emergency heat loads. Redundant trains of VC, including chiller units, are required to meet the single failure criteria.
The requested amendment adds an alternative Action for Modes 5 and 6 to
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immediately suspend activities that present a potential for releasing radioactivity j
that might require isolation of the control room. This places the plant in a condition l
that minimizes risk. The existing Action requires that the remaining operable VC train be placed in makeup mode of operation. This Action is intended to demonstrate that the remaining train is indeed operable, that no failures that would prevent-automatic actuation will occur, and that active failures would be readily detected.
i The proposed Action does not provide additional assurance that the remaining train of VC is operable; however, it does minimize the probability of the occurrence of an t
event that would require operation of the VC system. This Action is also consistent with the required Action for the more severe condition of having both trains of VC ~
inoperable. Therefore, the proposed alternative Action is considered to be equally remediating as the existing Action.
f Suspending movement ofirradiated fuel was added to Action b for Modes 5 and f
6 primarily for consistency with the proposed alternative for Action a. This change introduces an additional restriction which helps minimize the probability of an event that would require operation of the VC system. Therefore, this change is conservative in nature. In addition, for consistency with the wording in Action a, the word " changes" was replaced by the word " additions." This change is purely editorial.
The proposed changes are consistent with the revised Standard Technical Specifications for Wcstinghouse Plants (STS) (NUREG 1431, Revision 0). The STS provide a separate specification for control room chillers that allows one train to be inoperable for 30 days (Specification 3.7.13). The STS also includes Actions in Modes 5 and 6 that are similar to the changes proposed in this request.
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I In addition, removal of an obsolete footnote (for Braidwood Technical Specifications only) is requested. The footnote states that limiting Condition for Operation 3.7.6 is not applicable prior to initial criticality on Cycle 1. However, this l
Limiting Condition for Operation 3.7.6 has been applicable since May 1987, and l
therefore, this footnote is no longer required.
Impact of the Proposed Chance t
Technical Specifications require that both trains of VC be operable at all times.
The Action statement allows one train of VC to be inoperable for seven days before operating units must be shut down. Some types of maintenance involving the VC chiller unit can take longer than seven days. In particular, activities such as retubing or motor disassembly and rebuild of a VC chiller unit can take longer than currently allowed and could take as long as four weJras.
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The most significant potential for delay is parts availability. Although CECO l
Stores maintains replacements for most chiller components, certain parts are not kept in stock due to cost or because they are expected to remain serviceable for the life of the plant. Failure of such a coraponent, e.g. tube sheets or tube supports, could considerably extend the repair time. Depending on availability of these parts, procurement alone could take several weeks.
r Technical Specifications only allow one train of VC to be inoperable for longer than 7 days when both units are in Mode 5 or 6. However, for a number of reasons, l
i it is not practical to schedule both units to be shutdown at the same time. The most significant of these reasons is the impact on electrical distribution system planning.
Having both units off-line can result in a shortage of power and/or local grid voltage problems. Another concern for a dual unit outage is the increased manpower
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requirements during refueling and maintenance outages. The additional manpower i
fbr a maintenance outage on one unit would adversely affect the schedule for the j
maintenance or refueling outage on the other unit. Also, the required Action would l
restrict fuel movement and other refueling activities. The result would be extended outages for both units.
In addition, malftmetions of a VC chiller unit may occur during periods when no plant shutdowns are scheduled. Because of the relatively short Allowed Outage o
Time (AOT), a failure of a single chiller could result in the unplanned shutdown of two units. A dual unit shutdown such as this could be avoided if adequate time was i
available to make all necessary repairs and to allow increased preventative maintenance.
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Up to this point in time, CECO has been able to perform the necessary chiller maintenance within the AOT. However, during several maintenance outages it has been difficult to complete the scheduled work within the AOT. During one maintenance outage, a Temporary Waiver of Compliance (TWOC) was initiated
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internally when it appeared that a chiller unit would not be returned to service within seven days. Fortunately, the chiller was repaired within the AOT and the TWOC was not needed. The proposed changes would greatly reduce the potential need for a TWOC in the future.
j Several circumstances in the future may require a chiller unit to be out of service for longer than seven days. For example, it is expected that at some time during a chiller's service life, a complete overhaul will be required. This activity will take considerably longer than seven days. Also, modifications to the chiller units are expected to be required to meet new regulations concerning freon usage. These i
modifications will most likely require longer than seven days to complete.
l In addition to the length of the AOT, several other changes are requested.
Currently, with one VC train inoperable in Modes 5 or 6, the Action requires that the remaining operable train be run in makeup mode. Extended operation in makeup mode results in a reduced expected service life for the charcoal filter units. The proposed change would add an alternative Action for Modes 5 and 6 to immediately suspend activities that present a potential for releasing radioactivity. This Action reduces the probability of events that might require isolation of the control room.
This Action provides an alternative to placing the VC system in makeup mode, thereby extending the life of the charcoal filter units.
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The remaining change to Action b is primarily administrative and is requested for consistency with the proposed alternative added to Action a.
Schedule Reauirements There are currently no specific schedular requirements for the requested changes.
Identification and Discussion of Any Irreversible Consecuences i
No irreversible consequences will result from the proposed changes.
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