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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
Commonwealti: thon Gunpany liraidwood Generating Station i
Route
- l, llox H 1 liracesille. IL un07%19 Tel 3144%2801 Augu'st 23,1996 U.S. Nuclear Regulatory Commission Washington D.C. 20555 Attention: Document Control Desk
Subject:
Application for Amendment to Facility Operating Licenses:
Byron Nuclear Power Station, Units I and 2 NPF-37/66: NRC DeskelMcs. 50-454/455 Braidwood Nuclear Power Station, Units 1 and 2 NPF-72/77: NEC Docket No.s. 50-456/457 "Non-Accessible Area Exhaust Filter Plenum Ventilation System"
Reference:
1.
Teleconference between Commonwealth Edison, NRC Region III, and NRR on July 26,1996 Reference 1 discussed the need to revise Appendix A Technical Specification 3/4.7.7,"Non-Accessible Area Exhaust Filter Plenum Ventilation System," of Facility Operating Licenses NPF-37, NPF-66, NPF-72 and NPF-77, to reflect the design lineup for the Non-Accessible Area Exhaust Filter Plenum Ventilation System, and to make provisions for the performance of maintenance and testing on this system. During the referenced teleconference, Commonwealth Edison (Comed) committed to supply to the NRC an amendment to Technical Specification 3/4.7.7 within 30 days. Pursuant to this commitment, Comed is supplying the attached Application for Amendment to Appendix A, Technical Specifications, of Facility Operating Licenses NPF-37, NPF-66, NPF-72, and NPF-77.
This package consists of the following:
Attachment A Description and Safety Analysis of Proposed Changes to Appendix A Attachment B Proposed Changes to the Technical Specification Pages for Byron and Braidwood Stations Attachment C Evaluation of No Significant Hazards Consideration
)
Attachment D Environmental Assessment.
To the best of my knowledge and belief, the statements contained in this documeut are true and correct.
In some respects these statements are not based on my personal knowled e, but on information F
furnished by other Comed 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 Mr. Douglas iluston at k )
(815) 458-2801, extension 2511.
9608280184 960823 i
Sincerely, PDR ADOCK 05000454 fh1 01 P
PDR
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UFFICI AL S E A L" l '
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JACQUELINE A. SERENA lf
[ H. G. Stanley NOTARY PUBUC, STATE OF ILUN015 ll Site Vice President MY COMMISSION EXPIRES 5/14/97 g Braidwood Nuclear Station
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M"$4MP'">
1 cc:
A. B. Breach, Regional Administrator -IUII M. D. Lynch, Senior Projects Manager - NRR G. F. Dick Jr., Byron Project Manager - hTR R. R. Assa, Braidwood Project Manager - NRR S. Burgess, Senior Resident Inspector - Byron C. Phillips, Senior Resident Inspector - Braidwood Office of Nuclear Facility Safety - IDNS
1 a
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 l
A.
DESCRIPTION OF THE PROPOSED CHANGE Commonwealth Edison (Comed) proposes to amend Byron and Braidwood Technical Specification (TS) 3.7.7, "Non-Accessible Area Exhaust Filter Plenum Ventilation System," and the bases for this TS.
This mmendment will provide clarification of acceptable system lineups which satisfy the requirements of TS 3.7.7, and provide action requirements to accommodate required maintenance and surveillance activities.
The changes proposed in this request are discussed in detail in Section E of this attachment.
Copies of the affected TS pages with the changes indicated are included in Attachment B of this request.
B.
DESCRIPTION OF THE CURRENT REQUIREMENT TS 3.7.7 requires three independent non-accessible area exhaust filter (VA) plenums (50% capacity each) to be operable in Modes 1,
2, 3, and 4.
(
With one VA plenum inoperable, TS 3.7.7 requires that the inoperable plenum be restored to operable status within 7 days or place the plant in hot standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
C.
BASES FOR THE CURRENT REQUIREMENT The operability of the VA system ensures that radioactive materials leaking from the Emergency Core Cooling System (ECCS) equipment within the pump rooms following a Loss Of Coolant Accident (LOCA) are filtered prior to reaching the environment, i
The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses.
D.
NEED FOR REVISION OF THE REQUIREMENT I
The current TS does not reflect the VA system design lineup.
Under normal operating conditions, the VA system is designed to operate with two of the three VA filter plenums aligned. The third plenum is in standby. Each VA plenum consists of an inlet 1
damper, three parallel filter banks, two 100% capacity booster fans per plenum (six fans total) with discharge dampers on the outlet of each booster fan.
-In the event of a LOCA, the charcoal booster fans in the aligned plenums auto start to filter air from the ECCS pump cubicles.
The standby plenum receives the auto start signal, however, an interlock prevents the charcoal booster fan from starting with the inlet damper closed to prevent damage to the fan.
Should the standby plenum be required to operate, the inlet damper can be opened manually from the control room.
The charcoal booster fan would then start.
Under certain surveillance or corrective maintenance conditions, it is sometimes necessary to have one operable plenum aligned for operation. For example, a post maintenance test may require a flow test on a plenum prior to declaring it operable. This plenum must be aligned to accomplish this test. However, the system is not designed to have all three plenums in operation simultaneously.
Two plenums are required to achieve the minimum design basis flow for the non-accessible areas.
The flow is based on maintaining radiation doses As Low As Reasonably Achievable (ALARA) and temperature considerations for the non-accessible areas.
The ECCS pump rooms are cooled by dedicated room coolers.
Thus the desigr function of the VA system is to ensure the ECCS cubicles are kept at a negative pressure and any airborne post LOCA leakage is filtered prior to release.
Running the charcoal booster fans with all three plenums aligned could result in stalling the charcoal booster fans which could result in damage to the fans. To prevent this, it is necessary to align one of the plenums in standby, per system design.
Since the resulting lineup, one plenum in test and one plenum in standby, does not meet the revised Limiting Condition for Operation (LCO), it is appropriate to limit the amount of time this condition can exist.
Therefore, the TS should be revised to reflect the system design and establish controls over the conditions and the amount of time that only one operable plenum can be aligned.
E.
DESCRIPTION OF THE REVISED REQUIREMENT Comed proposes to revise the LCO for TS 3.7.7 to reflect the design lineup for the VA system.
The revised LCO reads:
"Three independent non-accessible area exhaust filter plenums (50% capacity each) shall be OPERABLE with two plenums aligned for operation and one plenum in standby."
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The action statement for TS 3.7.7 is revised to add provisions for maintenance and surveillance on VA plenums.
The revised action statement reads:
"With one non-accessible area exhaust filter plenum inoperable, restore the inoperable plenum to OPERABLE status within 7 days or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
During testing of any inoperable plenum, it is acceptable to place one of the two OPERABLE plenums in standby."
Finally, a paragraph is added to the bases section of TS to describe and axplain the basis for the design system lineup and the revised action statement.
The bases paragraph reads:
"The Non-Accessible Area Exhaust Filter Plenum Ventilation System is designed such that two plenums are on line and one plenum is in standby. A plenum is in standby if its inlet damper is operable but closed, and all remaining components are operable.
This alignment ensures proper air flow and prevents fan stall and possible fan damage.
The action statement provisions for standby plenums are necessary to accommodate required post maintenance and surveillance testing activities.
These provisions allow an operable plenum to be placed in standby while. performing testing on an inoperable plenum.
The standby plenum will still be capable of being realigned and filtering ECCS cubicle air in the event of a LOCA."
The affected TS pages indicating the proposed changes are provided in Attachment B.
F.
BASES FOR THE REVISED REQUIREMENT TS 3.7.7 is revised to reflect the design lineup for the VA system, and to provide action statement provisions to accommodate required maintenance and surveillance activities.
The VA system consists of three parallel plenums. Each of these plenums consists of an inlet damper, three parallel filter banks with a pre-filter, an upstream High Efficiency Particulate Air (HEPA) filter, a charcoal adsorber, a downstream HEPA filter, and two 100% capacity booster fans per plenum (6 fans total) with discharge dampers on the outlet of each booster fan.
The normal exhaust for the Non-Accessible Area Exhaust Filter Plenum Ventilation System is connected to the VA system between the upstream HEPA filter and the charcoal adsorber.
This connection is referred to as the charcoal adsorber bypass line.
These plenums are connected to the ECCS equipment cubicles and other non-accessible areas for both Units 1 and 2.
During' normal operation, the air from the ECCS equipment cubicles is drawn by the normal auxiliary building exhaust system through 3
)
i the VA inlet damper, the pre-filter, the upstream HEPA filter then out the charcoal adsorber bypass line upstream of the charcoal.adsorber and the downstream HEPA filter into the auxiliary building exhaust plenum.
The charcoal booster fans do not run under these conditions.
The normal, design lineup consists of two of the three filter plenums in service.
The plenum that is in standby has its inlet damper closed to minimize unnecessary filter and charcoal degradation during normal operation and to prevent exceeding VA system flow design limits, and possible stall of the charcoal booster fans should three charcoal booster fans start on an accident.
Following a LOCA, the charcoal adsorber bypass dampers close automatically and the charcoal booster fans are started.
The charcoal booster fans will start automatically on the Safety Injection (SI) signal if the inlet damper is open.
If the plenum is in standby, the fans will be started manually as directed by the emergency procedures.
The design basis acciden for the VA system is the LOCA with Loss 1
Of Offsite Power (LOOP).
On a LOOP, it is assumed that one i
diesel starts and re-energizes its Emergency Safeguards Features (ESF) bus.
Re-energization of the bus is required to take place within 10 seconds and the VA charcoal booster fans for the in service plenum start immediately.
The charcoal booster fans in each VA plenum are each 100% capable, and are powered from different ESF buses on the same unit for the A and B plenums, and from different units for the C plenum.
For example, Unit 1, plenum A fans are powered from ESF buses 141 and 142. Each of these buses has its own diesel.
Thus, on a LOOP, there will always be at least one VA plenum initially running.
Also, the emergency procedures direct the realignment of the standby plenum.
This direction is contained in Byron and Braidwood Emergency Procedure (BEP/BwEP)-0, " Reactor Trip or Safety Injection," and is performed prior to conducting event diagnostic steps.
Immediate realignment of the standby plenum is not necessary since filtration of the air from the ECCS cubicles is not critical until the suction of the ECCS pumps switches from the Refueling Water Storage Tank (RWST) to the containment recirculation sump.
This is postulated to occur, at the earliest, 11 minutes after event initiation.
Observations conducted on licensed operators undergoing simulator requalification training have verified that the emergency procedures realign the standby VA plenum well within the time constraints mentioned above.
Under certain surveillance or corrective maintenance conditions, it is sometimes necessary to have less than two operable plenums aligned for normal operation.
For example, a corrective maintenance item may require a flow test on a plenum prior to 4
declaring it operable.
This plenum must be aligned to accomplish this test.
However, the system is not designed to have all three plenums in operation simultaneously.
To prevent this, it is necessary to place one of the other operable plenums in standby.
The action statement for TS 3.7.7 is revised to accommodate this condition, while at the same time limiting its duration.
A review of the Byron and Braidwood Probabilistic Risk Assessment I
(PRA) model was conducted to assess the effect of these proposed changes on Core Damage Frequency (CDF) and Uncontrolled Release Frequency (URF).
This review showed that the VA system is not modelled in either the Byron or Braidwood PRA.
This is because I
the operation of the equipment necessary to prevent core damage is not dependant on the operation of the VA system.
In addition, the URF model does not take credit for the VA system.
G.
IMPACT OF THE PROPOSED CHANGE On the postulated LOCA with LOOP, the operating plenum will either realign immediately or following the re-energization of its ESF bus, which will occur within 10 seconds.
Thus, there will always be at least one VA plenum operating immediately during an accident.
The emergency procedures will direct the realignment of the standby plenum.
Filtration of the air from the ECCS equipment cubicles becomes critical when the ECCS pumps begin pumping accident water from the containment recirculation sump.
Prior to this, the water flowing in these pumps is RWST water.
This swap over from the RWST is expected to occur, at the earliest, 11 minutes following accident initiation, leaving time to realign the standby VA plenum.
Thus, since the standby plenum will be realigned before filtration of the ECCS equipment cubicle i
air is required, the Updated Final Safety Analysis Report (UFSAR) assumptions, and offsite dose calculation assumptions remain valid.
The realignment process is straightforward, procedurally directed, and readily accomplished entirely from the control room.
Observations conducted on licensed operators undergoing simulator training verified that the VA system is realigned well before the swap-over to the containment recirculation sump under these conditions.
The action statement provisions for standby plenums are necessary to accommodate required maintenance and surveillance activities.
These provisions allow an operable plenum to be placed in standby while performing testing on an inoperable plenum.
The standby plenum will still be capable of being realigned and filtering ECCS cubicle air in the event of a LOCA prior to the need for this filtration.
A review of the Byron and Braidwood PRA shows that these proposed changes will have no effect on either CDF or URF.
The proposed change will not require any new equipment to be installed nor will any existing equipment be modified.
No system 5
interfaces will be changed and no new operating modes will be created.
Design basis requirements will continue to be met.
Thus, th.ese proposed changes will have no significant negative impact on any system or operating mode.
H.
SCHEDULE REQUIREMENTS Byron and Braidwood Stations request that these proposed changes be approved in a timely manner.
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