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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 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 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 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 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 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 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 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 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 ML20096C0161996-01-11011 January 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS 3.3.1, RT Sys Instrumentation, Table 3.3-1,Functional Unit 6, Source Range,Neutron Flux, Consistent W/Improved STS ML20095J5081995-12-21021 December 1995 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,expanding Plant Operating Limits Rept to Include Limits Suggested by GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts ML20095D6191995-12-0606 December 1995 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3/4.6.1, Primary Containment, to Incorporate Requirements of Revised 10CFR50,App J,Which Became Effective on 951026 ML20098C6751995-10-0303 October 1995 Application for Amends to Licenses NPF-37 & NPF-66,revising Allowable Time Intervals for Performing Certain TS Surveillance Requirements on Plant Components During Power Operation,Per GL 93-05 ML20098A3851995-09-20020 September 1995 Suppl Application for Amends to Licenses NPF-37,NPF-66, NPF-72 & NPF-77,modifying TS 3.6.1.7, Containment Purge Ventilation Sys ML20092H3151995-09-14014 September 1995 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 5.3.1, Fuel Assemblies to Allow Use of Alternate Zirconium Based Fuel Cladding,Zirlo & TS 5.4.1.a to Refer to UFSAR Rather than FSAR ML20087H6881995-08-15015 August 1995 Application for Amends to Licenses NPF-72 & NPF-77,revising Ts,By Renewing Current 1 Volt SG Tube Plugging Criteria Per GL 95-05 ML20087E2521995-08-11011 August 1995 Suppl to Application for Amends to Licenses NPF-37,NPF-66, NPF-72 & NPF-77,revising TS 3.6.1.7, Containment Purge Ventilation Sys 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 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 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 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 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 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 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 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 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 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 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 ML20210K9661997-08-13013 August 1997 Amends 85 & 85 to Licenses NPF-72 & NPF-77,respectively, Authorizing Change to Realistic Dose Values for Process Gas Sys Rupture in Section 15.0 of Plant UFSAR ML20210M6581997-08-13013 August 1997 Amend 84 to License NPF-77,revising TS 4.5.2.b.1 to Clarify That Venting Only Required on ECCS Subsystems That Are Idle or Stagnant ML20149B7561997-07-10010 July 1997 Amends 91,90,84 & 83 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS 3.6.3, Containment Isolation Valves, to Reflect Mods Associated W/Sg Replacement for Unit 1 of Each Station 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 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 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 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 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 ML20138K0291997-05-0606 May 1997 Amends 89,89,81 & 81 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS to Permit Removal of Containment Tendon Sheathing Filler Grease in Up to 35 Tendons for Plants in Advance of SG Replacement Outages 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 ML20137Y0661997-04-16016 April 1997 Amends 80 to Licenses NPF-72 & NPF-77,respectively, Relocating Certain cycle-specific Parameter Limits from TSs to Operating Limits Rept 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 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 1999-09-08
[Table view] |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
'i Commonnealth Edison -
72 West Acams Stroet. CNcago, lihnos,
\\
Address Reply to. Post Othc0 Box 767 CNeago,Ilkros 60690 0767 y
July,31, 1989' l
i 1.
\\
I l
Dr. Thomas E. Murley, Director l
Office of Nuclear Reactor Regulation j
U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control'resk, I
Subject:
Braidwood Station Units 1 and 2 Application for Amendment to Tacility Operating Licenses NPF-72 and NPF-77 Appendix A, Technical Specifications t
NRC Docket Nos. 50-456 and 50-4S7
Dear Dr. Murley:
Pursuant to 10 CTR 50.$0, Commonwealth Edison (Edison) proposes to amend Appendix A,. Technical Specifications, of Facility Operating' Licenses NPF-72 and NPF-77.
The proposed scendment requests changes to Technical Specification 3.3.3.3 to provide a new location of the free field seismic monitor'for the time-history accelerograph. The current location of the' monitor is 39 + 00E and 41 + OOS. The proposed new location of the monitor is 38:+ 01S and 34 + 15E.
This relocation is being made due to the construction of a new Training Building in the area that includes the current monitor location. This work started on July 24, 1989.
The proposed amendment has.been reviewed and approved by Edison On-site and Off-site review in accordance with Edison precedures.
At Braidwood Station, four triazial accelerometers are' installed that individually measure the absoluto acceleration as.a function of' time in three orthogonal directions.
(See Attachment B for-a description'of the monitors and L
their locations). These monitors have a +2g to O to -29 range with a 0.0005V full l
scale resolution. The cross axis sensitivity is 0.0005 /g, accordingly. Three of 9
these accelerometers are installed on the containment and have the capability to' l;
sense and transmit data in the event that the containment floor accelerometer l
senses a 0.02g force. The fourth monitor is the free field monitor.
A fifth,-
1 totally. Independent monitor remains operable in the Essential Service Water (SX) pump room.
It is as sensitive as the other four monitors but is presently set to activate more conservatively at less than or equal to.029 force. During the time that the free field seismic monitor is being moved and, as such, will be inoperable, the remaining three triasial accelerometers, and the SX pump room monitor will continue to be operable. These remaining-operable monitors will be in a condition to provide the data necessary to access the impact of.any seismic events on plant systems and structures to allow for safe operation of the plant.
9009060151 900731 ONS; i
PDR ADOCK 05000456 gO(
p PNV l
Dr., T.M. Murley 2 -
July 31, 1989 Tochnicc1 Sp3cification 3.3.3.3 stotos that with ono or msro of tho required seismic monitors inoperable for more than 30 days, prepare and submit a special report to the commission, pursuant to Specification 6.9.2, within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status. The 30 day limiting condition for operation (LOCAR) for the free field monitor was entered on July 24, 1989.
The free field I
monitor is being physically moved to the new location, but will be functional and available for service by August 11. 1989.
At that time, the free field monitor will be " administratively inoperable" until the Technical Specification Amendment is received.
Since the proposed snendment cannot be r9asonably issued within the 30 days following the disablement of the monitor, Edist'n will forward a special report to the commission as required, outlining the situation and the plans to restore the monitor to OPERABLE status in the new propcsed location.
Because other monitors remain operable, as described above, ad9quate seismic monitoring capability exists during this period.
This is also addressed in Attachment B.
Edison's proposed amendment request is subdivided as follows:
1.
Attachment A gives a s nt'ary of the changes proposed in the snendment including pleitclal views that show the new location of the monitor with respect to the old location.
2.
Attachment B provides the Safety Evaluation and Environmental Assessment.
3.
Attachment C describes Edison's evaluation performed in accordance with 10 CTR 50.92(c), which has determined that no significant hazards considerations exist.
4.
Attachment D 1:sludes the marked-up Technical Specification pages with the requested changes indicated.
Edison is notifying the State of Illinois of this application for amendment by transmitting a copy of this letter and its attachments to the designated State Official.
Please direct any questions you may have concerning this submittal to this office.
Very truly yours, l (. f _
J u S.C. Hunsader Nuclear Licensing Administrator l
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Att.'s:
A)
Summary of Proposed Changes B)
Safety Evaluation and Environmental Assessment C)
Evaluation of Significant Hazards Considerations D) Marked-up Technical Specification Pages
Enclosures:
1,2 and 3 cc Resident Inspector-Braidwood S.P. Sands-NRR J. Hinds-Region III M.C. Parker-IDNS
AIIACHMENT.A.
-l SIDE (ARY_Or. PROPOSED CHANGES TO APPENDIX A TECHNICAL SPECITICATIONS Or FACILITY ' OPERATING LICENSES NPF-72 AND NPr.77
-l The proposed changes to Technical-Specification 3.3.3.3 indicate the new location of the free field seismic monitor.
Due to the construction of a new.
Training Building in the area that includes the free field' seismic monitor, it must be relocated. The current coordinates of the free field monitor are 39+00E and 41+00S.
This location is approximately 250 feet south of the southwest corner of the Braidwood Station protected area fence.
The proposed new location of the free 7
field monitor is 38+015 and 34+15E.
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The vendor (Terra Technology, Inc.) recommendations state that the free field monitor be located a minimum of 200 to 250 feet from any heavily travelled roads or major structures.
In accordance with these recommendations, the proposed location for the free field monitor will place it 294 feet west of the center line of Braidwood Station entrance road, and over 400 feet from the Braidwood Station Turbine Building outerwall (the nearest major structure).
Two photographs are enclosed to show the current and proposed location of the free field monitor.
These are provided as Enclosures 1 and 2.
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- s ATTACHMENT B SAFETY EVALUATICDI AND ENVIRONMENTAL ASSESSMENT FOR PROPOSED CHANGES TO APPENDIX A' TECHNICAL SPECIFICATIONS OF EACILITY OPERATING LICENSES NPF-72 AND NPF-77 SAFETY EVALUATION in(Loduction The purpose of the seismic instrumentation is to insure that sufficient-capability is available to promptly determine the magnitude of a seismic event, and
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evaluate the response of features important to safety. This comparison is necessary in order to compare the magnitude of the event'to the design basis event to determine if a plant shutdown is required.
The seismic' instrumentation utilizes two types of sensor-recorders, with a-playback capability available in the control room area. The location.and function of these seismic devices were selected to provide, adequately, for the determination of saismic event loads into the structures via computerised analysis programs. The system is maintained during a loss of ac power by a backup de power supply.
Loss of ac power operation is alarmed locally and in the main control room.
Byron /Braidwood UFSAR Section 3.7.4 describes the functiJns of the seismic instrumentation including the time-history accelerograph to which the free fleid seismic monitor of' interest is connected.
Time History Accelerocraph The time-history accelerograph is the master control unit for all control-timing signals and system data interface.
It continually monitors and has the ability to digitize voltage signals and record on magnetic tape both pre-and post-seismic event data.
Integral to-the accelerograph are two triasial seismic triggers which provide.a signal to actuate a local alarm on the' seismic warning panel during a seismic event. These trigger inputs are continually monitored by the accelerograph.
There art two time-history accelerographs utilised as part of l
the seismic instrumentation.
The time-history accelerograph located in the auxiliary electric equipment room receives inputs from four. triaxial monitors, each of which measures the l
absolute acceleration as a function of time in three orthogonal directions.
These directions' coincide with the major axes of the analytical model of the structure.
The second time-history accelerograph and'its monitor at Braidwood is provided at' elevation 338 feet 0 inch in the auxiliary building on the column row 18 wall i
l adjacent to the column line "L" wall.. This accelerograph is a self-contained unit l
independent of the other accelerograph. The response spectrum for this' location can be determined using the playback unit and response spectrum analyser.
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ATTACHMINT B fcontinvidl The first time-history.accelerograph is connected to four trianial
?ccelerometers, each of which measures the absolute acceleration as a function of tice in three orthogonal directions.
These directions coincide with the major axes of t.5e analytical model of the structure.
These accelerometers are placed at the folloving locations:
1.
In the free field, currently at site coordinate 39+00E and 41+00S, to be moved to site coordinate 38+c?S and 34+15E, 2.
on the containment building foundation slab at elevation 377 feet and azimuth 145 degrees, 3.
on the containment shell wall at elevation 502 feet and azimuth 145 degrees, and 4.
on the containment '.efueling floor at olevation 426 feet.
l The safe shutdown value for Braidwood Station is 0.2 9 As such, the l
configuration of the seismic monitor syatem conforms to that addressed in l
Regulatory Guide 1.12 and ANSI Standard.N18.5 for a= plant with safe shutdown acceleration of less than or equal t o ;9.3' g.
Also, the soil and subsurface conditions a4 Braidwood Station are relatively uniform.
(This is discussed in UFSAR Section 2.5.4 and is graphically depicted by UFSAR Figure 2.5-21.
A copy of rigure 2.5-21 is provided as Enclosure 3.)
Thus, the response of the free field monitor to seismically induced ground motion will not be altered by the monitor's change in location.
Control Room Operator Notification The centrally located seismic indicating and recording equipment near the main control room is the source of the operator information concerning the acknowledgement of an earthquake. An acceleration of 0.02g in any direction activates the seismic switch which turns on the seismic monitors and lights up the the seismic alarm lights at the seismic warning panel.
Using the spectrum analyzer (see UFSAR Section 3.7.4.2.4), an operator can observe the triaxial cpectral analysis from the containment building slab monitor l.
and the auxiliary building 426 feet elevation monitor.
(The latter monitor is direct-connected to the spectrum analyser, while the former monitor is connected to the analyser through the time-history accelerograph.)
The operator can also use the playback feature of the system to obtain time history and spectral analysis of any of the recorded monitors.
1 Summary
(
Safety related equipment and features will be unaffected by the placement of the-free field monitor. The proposed. change to the free fleid monitor location conforms to the guidance given in Reg Guide 1.12 and ANSI N18.5.
Adequate monitoring capability will continue to exist.to^ assess the affects of a seismic event on equipment and features important to safety, both during and after L
relocation of the free fleid monitor, SCH/sc1:0218T 5
=am a
ATTACMMENT B (continued)
ENVIRONMENTAL ASSESSMENT Edison has evaluated the proposed amendment against the criteria for and
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identification of licensing and regulatory actions requiring environment assessment l
In accordance with 10CTR51.21.
It has been determined that the proposed change meets the criteria.for a categorical exclurlon as provided for under 10CTR51.22(c)(g).
This determination was based on the fact that this change is being proposed as an-amendment to a license issued pursuant to 10CTR50 a:.d the change involves changes to the use of components located within the restricted area, and it involves no significant hazard considerations. There are no changes in the type or enounts of effluents related Off-site, and there is no significant increase in individual or cumulative occupational radiation exposure.
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-ATTACHMENT C EVALUATION OF_ SIGNIFICANT ~ HAZARDS CONSIDERATICMS FOR PROPOSED CHANCES j
TO APPENDIX. A TECHNICAL SPECIFICATIONS OF l
i
[AC11JTLQEERATING LICENSES NPF-72 AND NPF-77 I
Commonwealth Edison has evaluated this proposed unendment and determined-that it involves no significant hasards considerations.
According to 10 CTR.
50.92(c), a proposed unendment to an operating license involves no significant hazards considerations if operation.of the facility in accordance with the proposed amendment would not I
1.
Involve a significant; increase in the probability or consequences of i
an accident previously evaluated; or t
2.
Create the possibility of a new or different kind of accident from
-j any accident previously evaluated; or 3.
Involve a significant' reduction in a margin of safety.
I A.
The proposed chance does not involvt_a_glanificant increase in the probability or consequences of an accident oreviously evaluated.
.i The relocation-of the seismic monitor has no impact on the probability for accidents or seismic events.
Equipment and plant features important to safety will respond in the same f ashion.to a seismic event regardless of pre-monitor location. As a result,.the proposed change does aot result in a significant increase in the probability or-consequences of accidents previously evaluated, i
B.
The oronosed changes does not create the prossibility of a new or different i
Lind of neeldent from any accident o_reviousiv evaluated.
The seismic monitors are not active components taken credit for in any accident analysis.
The purpose of the monitors is to provide information regarding the magnitude'of a seismic event.
This information would then be used to assess any impact on. continued operation of the facility.
The soil and subsurface conditions at Braidwood Station are relatively uniform. Thus, the response of the free field monitor will not be significantly different at the proposed new location as compared toilts current location.
The proposed location for the free field monitor does not impact the operability of any equipment required for safe operation of the plant during normal or accident conditions.
As such, the proposed change does not create the possibility for a new or different kind of accident from those previously evaluated.
C.
The proposed chance does not involve a sionificant reduction in a maroin of safety.
l The operation of the' seismic monitoring system is not taken credit for in any accident analysis described in the UTSAR.
The relocation of the seismic
'f l
monitor does not affect any accident analysis.
As such, the proposed change does not involve a reduction in.the margin to safety..
SCH/sc1:0218T:7
i ATTACHMENT D MARKED +UP PAGES FOR PROPOSED CF1ANGES TO APPENDIX A TECHNICAL SPECIFICATIONS OF I
TACILITY OPERATING LICENSES NPT-72 AND NPT-77
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s REAIDWOOD STATION Revised Pagest 3/4 3 B3/4 3-4 i
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