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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
,
fO Commtnwnith Edison
) 1400 Opus Place
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'O Downers Grove. Illinois 60515 June 13,1994 l
Mr. William T. Russell, 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 Licenses:
Byron Station Units 1 and 2 NPF-37/66; NRC Docket Nos. 50-454/455 Braidwood Station Units 1 and 2 1
NPF-72/77; NRC Docket Nos. 50-456/457
" Administrative Changes" Dear Mr. Russell.
Pursuant to 10 CFR 50.90, Commonwealth Edison Company (Comed) proposes to amend Technical Specifications of Facility Operating Licenses NPF-37, NPF-66, NPF-72 and NPF-77. The subject amendment request proposes to revise Section 6,
" Administrative Controls", addressing (1) the submittal frequency of the Radiological Effluent Reiease Report, (2) the Shift Technical Advisor description, (3) clarification of the Shift Engineer's responsibilities, and (4) other editorial changes to improve
)
readability and consistency with station procedures.
A detailed description of all proposed significant changes is presented in Attachment A. The site specific revised Technical Specification pages are contained in Attachment B.
1 The proposed changes have been reviewed and approved by the applicable i
station On-site Review Committee and the Off-site Review Committee in accordance with Comed procedures. Comed has reviewed this proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no significant hazards consideration exists as documented in Attachment C. An Environmental Assessment has been completed and is contained in Attachment D.
j nan,nn 9406220306 940613 PDR ADOCK 0500 4
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4 j
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Mr. W. T. Russell 2
June 13,1994 Comed is notifying the State of Illinois of our application for these amendments by transmitting a copy of this letter and the associated attachments to the designated State Official.
To the best of my knowledge and belief, the statements contained in this document are true and correct, in some respects these statements are not based on my r
personal knowledge, but on information 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 comments or questions regarding this matter to this office.
j
- =:= =::=:=::::n, Respectfully, OFFICIAL SEAL l;
[.
ad MARY JO YACK k
pe NOTARY PUBUC, STATE OF ILLINotSl 5*ESYIY'0:7.'-)E5-$_UE$'ll Joseph A. Bauer l
Nuclear Licensing Administrator
'0}y 1 s O,
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,I l Attachments cc:
G. F. Dick, Byron Project Manager - NRR R. R. Assa, Braidwood Project Manager - NRR H. Peterson, Senior Resident inspector - Byron S. G. Dupont, Senior Resident Inspector - Braidwood B. Clayton, Branch Chief - Region Ill Office of Nuclear Facility Safety - IDNS l
4 ATTACHMENT A DESCRIPTION AND SAFETY ANALYSIS OF PROPOSED CHANGES Description of the Proposed Changes Commonwealth Edison Company (Comed) proposes to revise Section 6, Administrative Controls, of Technical Specifications for Byron and Braidwood stations.-
The proposed changes include (1) a change to the submittal frequency of the Radiological Effluent Release Report, (2) a revision to the Shift Technical Advisor description, (3) clarification of the Shift Engineer's responsibilities, and (4) editorial changes.
The marked up Technical Specification pages for each station indicating the proposed changes are provided in Attachment B. A discussion of each proposed change is given below.
1.
Proposed Change to Submittal Frequency of Radiological Effluent Release Report Description and Bases of the Cunent Reauirement The Radiological Effluent Release Report is submitted semiannually based on the requirements of 10CFR50.36a (prior to August 31,1992).
Description and Bases of the Requested Revision Commonwealth Edison proposes to reduce the requirements for the submission of the Radiological Effluent Release Report from semiannual to annual for Byron and Braidwood. This change affects the index, and Technical Specifications 1.18, 3.11.1.4, 3.11.2.6, 6.9.1.7, and 6.14.1. This change is consistent with the final rule for reducing the regulatory burden on nuclear licensees that was published in the Federal Register on August 31,1992. The rule change included a revision to 10CFR50.36a regarding the frequency for submitting radiological effluent reports. This change is also consistent with the guidance provided in Draft Generic Letter, "Guldance for Modification of Technical Specifications to Reflect Revisions to..10CFR50.36a..."
Impact of the Proposed Chance This change is administrative in nature and makes the Technical Specifications consistent with the amended requirement of 10CFR50.36a and the draft generic letter. The change does not adversely impact the ability to meet applicable regulatory requirements related to liquid and gaseous effluents. The proposed change will eliminate an unnecessary administrative burden without reducing the protection of the public health and safety.
F i
Attachment A Page 2 4
2.
Proposed Change to the Shift Technical Advisor Description
_D_qspription and Bases of the Current Reauirement Technical Specification 6.2.4 describes the purpose of the Shift Technical Advisor j
(STA) and how capability for performance of STA functions is assured. The Station Control Room Engineer may serve as the STA during abnormal operating or accident conditions.
Decedpiion and Bases of the Reauested Revinktu Ihe proposed change deletes redundant / unnecessary text in Technical l
Specification 6.2.4 except for the description of the STA function. The deleted i
text addresses the interface of the STA with other control room personnel. The deleted material is currently controlled in station administrative procedures and the UFSAR, and is not required in the Technical Specifications to meet regulatory requirements. The STA qualifications are specified in footnote (c) of Table 6.2-1.
The proposed change is consistent with the STA description in the Standard Technical Specifications for Westinghouse Plants (NUREG 1431).
l Impact of the Proposed Chanae The proposed change allows for the flexibility of multiple shift crew configurations and is consistent with the Standard Technical Specifications. The current interpretation of the STA Technical Specification requirements is that the SCRE is the only position that may function as the STA. The proposed change will allow any on-shift SRO, who meets STA qualifications, to perform the STA duties.
The STA requirements of NUREG-0660, Action item I.A.1.1, as clarified by NUREG-0737, remain satisfied. If an on-shift Individual holding a Senior Reactor Operator license is filling the STA position, relief from licensed duties and assumption of the STA function is governed by station administrative procedures.
3.
Proposed Clarification of the Shift Engineer's Responsibilities Descriotion and Bases of the Cunent Reauirement Technical Specification 6.1.2 states that the Shift Engineer shall be responsible for the control room command function and requires that a management directive to this effect, signed by a company executive, be issued to all station personnel on an annual basis. The Specification also requires that a designated individual shall maintain control room command during the Shift Engineer's absence from the control room.
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E Attachment A Page 3 Description and Bases of the Requested Revision The proposed change specifies that the Shift Engineer is responsible for directing the control room command function and the daily operations of the facility. The issue of transferring control of the command and control function during the Shift Engineer's absence is addressed by footnote (f) of Table 6.2-1. The proposed 1
change is made to more clearly define the responsibilities of the Shift Engineer.
i The requirement to issue the annual management directive that describes control room command is deleted from the Technical Specifications. This change eliminates an unnecessary administrative requirement that has no effect on safe operation of the plant.
Impact of the Proposed Chanae The Shift Engineer is responsible for the safe overall operation of the facility at all times, regardless of his physical location in the plant. This responsibility is more inclusive than the control room command function. Stating that the Shift Engineer is responsible for the control room command function implies that the majority of the shift is spent in the control room, which is usually not the case. At Byron and Braidwood, the Shift Engineer's office is located adjacent to, but not within, the control room envelope. The responsibility for the control room command function is delineated in footnote (f) of Table 6.2-1. An on-shift SRO, assigned to the control room, will normally be responsible for the control room command function.
Deleting the requirement to issue an annual management directive signed by an executive restating the responsibility of the Shift Engineer, removes an unnecessary administrative burden and has no effect on the safe operation of the facility. The Shift Engineer's responsibilities are described in approved station administrative procedures.
4.
Proposed Editorial Changes Description and Bases of the Reauested Revisions i
i Table 6.2-1 is reformatted to more closely match the minimum shift crew composition table provided in Standard Technical Specifications. The table includes more generic titles such as SRO and STA. Throughout Section 6, the titles of " licensed operator' and " senior operator" are changed to " licensed reactor operator" and ' senior reactor operator" to reflect current terminology.
Attachment A Page 4 4
Section 6 uses the term " unit" to mean " Unit 1 and Unit 2."
in these cases, " unit" is changed to " facility" for clarity. For example, the Shift Engineer function applies to both units, therefore, the word " facility' is used.
I In Specification 6.3, the specific titles of Health Ph'ysics Supervisor and Lead Health Physicist are replaced by a more generic description of the person who fulfills the position of the Radiation Protection Manager. Using a non-specific title will avoid the need to burden the NRC Staff with another Technical Specification amendment should organizational changes occur in the future.
1 Specification 6.8.3 contains a typographical error in the word " Specification." The proposed change corrects this error. The last sentence in Specification 6.9.1.4 is i
deleted since the initial annual reports have already been submitted for each l
station and the information is no longer required.
impact of the Proposed Chanos The proposed changes are editorial / administrative in nature, and do not reduce the requirements of any Technical Specification. They improve readability and i
provide consistency with station procedures and company programs.
i Schedule _Be.Quitaments There are no specific schedule requirements.
l Identification and discussion of any irreversible consecuences There were no irreversible consequences identified.
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2 ATTACHMENT B-1 PROPOSED CHANGES TO APPENDIX A, TECHNICAL SPECIFICATIONS, OF FACILITY OPERATING LICENSES NPF-37 AND NPF-66, BYRON STATION UNITS 1 & 2 Revision to:
XIX XX 1-4 3/4 11-1 3/4 11-3 6-1 6-2 1
6-2a 6-5 6-6 6-17 6-20 6-22 6-24
-l 6-27
CHANGE
SUMMARY
Technical Described Soecification Change Descriotion in item ft Index Change " unit' to " facility' 4
Index Change " Semiannual' to " Annual" 1
1.18 Delete " Semiannual' 1
4 3.11.1.4 Delete " Semiannual" 1
3.11.2.6.a Delete "Semlannual" 1
6.1.1 Change " unit' to " facility' 4
9 6.1.2 Revise description of the Shift Engineer's 3
responsibilities 6.2.1 Change " unit' to " facility" 4
6.2.2 Change " unit" to " facility' 4
Change " Operator" to " Reactor Operator" 1
6.2.4 Revise description of Shift Technical Advisor; 2
Delete description of specific STA work practices V
Table Replace table with one that is more consistent 4
6.2-1 with the Standard Technical Specifications d
(titles, notes, and format) 6.3 Change " unit" to " facility' 4
Replace specific titles with more generic titles 6.4 Change " unit' to " facility" 4
6.8.3 Correct spelling of " Specification" 4
6.8.3.b Change " Operator" to " Reactor Operator' 4
1
CHANGE
SUMMARY
(continued)
Technical Described
.Soecification Change Descriotion in item #
6.9.1.4 Change " unit" to " facility' 4
Delete reference to initial report
.6.9.1.6 Change " unit" to " facility' 4
6.9.1.7 Change the submittal frequency of the 1
radiological effluent report from semiannual to annual. Due date changed to May 1.
6.9.10.2 Change " unit' to " facility' 4
6.14.1.c Delete "Semlannual" 1
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