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Category:OPERATING LICENSES-APPLIATION TO AMEND-RENEW EXISTING
MONTHYEARML20209B7301999-06-30030 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 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 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 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 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 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 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 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 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 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 ML20086D9911995-07-0707 July 1995 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,increasing Interim Plugging Criteria for hot-leg Tube Intersections W/Outside Diameter Stress Corrosion Cracking from 1.0 Volt to 3.0 Volt 1999-06-30
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20209B7301999-06-30030 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 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 ML20198C2961997-12-30030 December 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.7.1.3, Condensate Storage Tank & Associated Bases for Plants to Raise Min Allowable CST Level ML20198H7521997-12-29029 December 1997 Errata to Amend 94 & 94 to Licenses NPF-37 & NPF-66, Correcting Typo That Was Inadvertently Introduced on TS Page 5-5 ML20199A4651997-11-0707 November 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively.Amends Would Revise TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.b & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20198J9301997-10-16016 October 1997 Application for Amend to License NPF-37,requesting Exemption from Requirements of 10CFR70.24(a), Criticality Accident Requirements. Request Is Being Docketed to Reflect Units 1 & 2 So That Amend Numbers Remain Identical ML20202F4481997-10-10010 October 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Convert Byron & Braidwood Current Tech Specs to Byron & Braidwood Improved Tech Specs ML20211D9341997-09-24024 September 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Allowable Time Interval for Performing Turbine Throttle valve.Non-proprietary & Proprietary Trs,Encl.Proprietary Info Withheld ML20216G8341997-09-0808 September 1997 Application for Amend to TS 4.5.2.b & Associated Bases to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,to Bring Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in 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 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 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 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 1999-06-30
[Table view] |
Text
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,ON Conwnonwealth Edison 4 / -
) Oni Fwst N;tional Pina, Chic:go, liimosa i
(N O Address Reply to: Post Office Box 767 Chicago. Illinois 60690 January 28, 1985
-Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Byron Generating Station Units 1 and 2 Braidwood Generating Station Units 1 and 2 Control Room Pressurization NRC-Docket-Nos. 50-454/455 and'50-456/457
Dear Mr. Denton:
This letter is to inform the NRC of changes to the Byron /
Braidwood control room HVAC systems and to propose appropriate revisions to the Technical Specifications. NRC review of these changes is necessary to finalize the Technical Specifications which
=will be incorporated into the Byron 1 full power operating license.
Recent testing at Byron Station indicates that the makeup air supply fans in the control room HVAC system do not'have adequate capacity to maintain a positive pressure of 1/8" w.g. in the entire control room HVAC envelope during all situations. Most of the relevant test data is summarized in Attachment A to this letter. 'h e required pressure cannot be maintained in all areas during the per od when Unit I is in operation and Unit 2 is still under construction.
Completion _of Unit 2 requires that penetrations be opened for the installation of cables, etc. The installed supply fans do not have the capacity to compensate for the extra air loss through those open penetrations. Administrative limits on the number or size of open p.enetrations would delay the completion of Unit 2.
Pressurization of certain rooms within the control room HVAC envelope is not needed for any safety reason. The cable spreading areas are not continuously manned and have no significant internal heat load. Eliminating these areas from the pressure boundary will make it possible to meet the 1/8" w.g. pressurization requirement with no adverse impact upon safety.
The lower cable spreading rooms will no longer be ventilated-by the control room HVAC systems. The connecting ducts will be blanked off or removed. Without air conditioning the temperatures in these rooms may be slightly higher. Our calculations indicate it could be as high as 106.5 F in the limiting design basis situation.
This will-not pose an environmental qualification problem for any of the components (principally cable) in this area. The temperature limit imposed in Table 3.7-6 of the Byron Technical Specifications should therefore be revised from 90'F to 108'F. An appropriately OMg
4
.. ?
H. R. Denton January 28, 1985 revised version of this table is included in Attachment B to this letter. Because air.will no longer be supplied to this space, the minimum' capacity of the HVAC recirculation system should also be revised. That revision is also included in Attachment B.
The upper cable spreading rooms will remain as part of the control-room envelope, however, on a temporary basis this area will be maintained at-a slight positive pressure. This will allow the i
installation of Unit 2-cables to proceed without delay. A reduction in.the positive pressure in the' upper cable spreading rooms will not threaten plant safety.- Fire protection research has shown that small differential pressures will eliminate air inflow through large openings such as doors. This is discussed.in more detail in Attachment A to this. letter. To assure that there-is no infiltration into the upper cable spreading rooms during Unit 2 construction, the pressure of ;
these areas will be maintained at least 0.02" w.g. above the adjacent
-auxiliary building and turbine building areas. The appropriate revised pages for the Technical Specifications are provided in Attachment B.
In the event that potentially contaminated air did infiltrate the upper cable spreading rooms, it is unlikely that the control room operators would be exposed to it. This space is not continuously manned and there is no ductwork returning air directly from these areas to the control room HVAC system. Although control room return air ductwork passes throu these ducts are sealed and duringanaccidentallrekhthisspaceurnairisfIlteredbycharcoaladsorbers prior to entering the control room.
These matters have already been discussed by telephone with the NRC Staff. Please direct questions regarding these matter to this office.
One signed original and fifteen copies of this letter and the s Attachments are-provided for NRC review. Appropriate revisions to the !
FSAR will be made at the earliest opportunity.
Very truly yours, T. R. iramm
- clear Licens' ministrator i Im i
lec t Byron-Resident Inspector 9684N
r i , 4* Page 1 k
ATTACHMENT A Background information is provided explaining the process of establishing the differential pressure in the Byron Station Control Room envelope to a level 1 0.125" WC.
Recognizing that Unit #2 is still under construction, information is pre-sented to show that in the interim between Unit #1 start-up and Unit #2 completion the requirement for maintenance of 3L 0.125" WC pressure in the upper cable spreading room can be relaxed to 0.02" WC.
BACKGROUND In evaluating the incremental changes in average control room pressure, a review of selected test points was made. This is discussed in Appendix A, " Control Room Pressure Evaluation". The changes in pressure as various tests were performed is summarized in Table 1, " History of Byron Control Room Pressure".
The Control Room envelope consisted of:
. Control Room, Auxiliary Electric Equipment Room, HVAC Equipment and other miscellaneous rooms on the 451'-0" elevation.
. The Upper Cable Spreading Room on the 463'-5" elevation.
. The Lower Cable Spreading Room on the 439'-0" elevation.
These are shown in Figure 1 and Figure 2. I This analysis began with the re-test of the Control Room HVAC System pre- .
operational test, at which ti.me the average pressure in the Control Room was 0.04" WC.
Since the Control Room HVAC System appeared marginal in establishing a minimum pressure of 0.125", Byron Station Construction Department began a comprehensive staged review of all penetrations of the Control Room envelope. The first review identified door seals that needed improve-ment and it was visually apparent that a number of penetrations and construction joints needed improvement. Once these items were finished, the average pressure in the Control Room rose to 0.08" WC (Table 1 Item B). At this time, the construction access hatch between the Con-trol Room and the Upper Cable Spreading Room was open. This hatch was sealed and the average Control Room pressure rose to 0.15" WC (Table 1, Item C).
During our meeting with the NRC in Bethesda on December 18, 1984, it was agreed that in order to improve the ability of the Control Room HVAC System to pressurize the Control Room Envelope, the Lower Cable Spreading Room was deleted from the Control Room Envelope (reducing the Control Room volume by approximately 1/3 and increasing the air available for pressuri-sation by approximately 22%), in addition, the local area exhaust from the toilet, storage and locker rooms and kitchen was removed and replaced with odor absorbing recirculation units (increasing the air available for pressurization by approximately 17%). This represented a combined increase of approximately 39% in air available for
_a
,. ,. Page a pressurization. The supply duct to the lower cable spreading room and the exhaust ran discharge ducts were blanked-off. This resulted in an average control room pressure of 0.18" WC (Table 1, Item D).
The Control Room Envelope was then surveyed utilizing a portable smoke generator to detect leaks that were not visually identifiable.
The identified leaks were sealed and this resulted in an average control room pressure of 0.20 WC (Table 1, Item E).
Experience has shown that once primary leak paths are sealed, second-ary or minute leak paths become evident. Recognizing this, the control room envelope was surveyed again. As expected, additional leak paths were identified with the portable smoke generator. These were sealed and the average control room pressure i rose to 0.28" WC (Table 1, Item F), which is 125% greater than the minimum 0.125" WC required.
The results of this test also demonstrated that the upper cable spreading room pressure was 0.21" WC with respect to the Turbine and Auxiliary Buildings. We, therefore, have physically demonstrated that the control room envelope is capable of being maintained at greater than the design minimum pressure of 0.125" WC.
UNIT 2 CONSTRUCTION -
On December 20, 1984, Byron Station Construction Department issued a Site Instruction to all Site Contractors, advising them of the re-quirement for requesting and/or identifying impairments in all fire /
radiation barriers specifically identifying the Control Room Envelope.
This was done to ensure that Station personnel are advised of any such impairments so that compensatory measures could be taken to maintain plant Technical Specifications and Rad / Chem requirements.
In order to complete Unit #2 construction, there are approximately 1100 electrical cables that must be pulled into the Control Room.
To provide a reasonable degree of flexibility in the maintenance of Control Room pressure we propose the following:
- 1. The Control Room complex on elevation 451'-0" will be maintained at an average positive pressure of 0.125" WC.
- 2. The Upper Cable Spreading Room on elevation 463'-5" will be maintained at an average positive pressure of approximately 0.02" WC.
JUSTIFICATION In a series of tests on building stairwell pressurization conducted by the ' Center for Fire Research of the National Bureau of Standards (NBS)
(Refer to Appendix B " Stairwell Pressurization"), it was determined that under a smoke candle test, with two doors open (approximately 42 ft.'), the average stairwell pressure was 0.014" WC. This was sufficient to demonstrate that smoke was not visible in the stairwell and that only the faint odor of smoke could be detected in the stair-well. The researchers state that a pressure of 2.5 Pa (0.01" WC) was sufficient to prevent infiltration of cold smoke.
T f ,y Page 3 2
' This information is presented to show similarity in design concept between the stairwell design (typically masonary construction with fire doors) and the Upper Cable Spreading Room (masonary and con-crete construction with fire doors).
Since the date of the final average pressurization readings in this
. report (12/27/84) construction of Unit #2 has progressed. On January 14, 1985 we performed pressure test similar to what we performed by NBS (without the smoke candle) utilizing two doors on 463'-5" elevation. Several openings in the control room envelope had been made to facilitate cable pulling. Of these openings, the two most notable were 17" x 38" (4.5 f t.') on elevation 463'-5"
.and 18" x 12" (1.5 ft.') on elevation 451'-0". The Control Room HVAC System was operating without the emergency make-up air filter unit ~ running (4400 CFM of make-up air rather than 5700 CFM). During the initial set of readi Spreading Room was 0.035jgithe WC with aaverage pressure local pressure in the of 0.01" WCUpper Cable across one of the fire doors on elevation 463'-5" near the 4.5 f t.'
penetration. At this time, the airflow from the Upper Cable Spread-ing Room to the adjacent stairwell could be felt three to four feet.
from the opening.
This test is summarized in Appendix C, " Upper Cable Spreading Room (UCSR) Pressure Test". Although the initial pressure was low
~(due to construction openings), the results paralleled the NBS tests.
The information presented demonstrated that large penetrations (approximately 20 ft.8) can be made in the control room envelope and still maintain the desired pressure level. Our intention is not~
to limit penetration areas but rather use average differential pressure to gauge the extent of penetrations allowed.
The design of the Control Room HVAC System is.such that all air. ~
supplied to the Upper Cable Spreading Room is expended in pressuri-zation. . There is no return air from the upper cable spreading room to the system. In the unlikely event that any contaminants migrate into the upper cable spreading room and are induced into
.the return ductwork, this air will be passed through the 90% effi-cient recirculation charcoal adsorber befor re-entering the Control Room Envelope.
Ensuring that the Upper Cable Spreading Room is under a positive pressure should pose no threat to Control Room operator safety under norinal or accident conditions.
w__-_____.
APPENDIX A CONTROL ROOM PRESSURE EVALUATION In order to provide a consistent basis for the evaluation of the relative changes in Control Room pressure four measurement points were selected. These points were chosen because the Control Room pressure would not be affected by the operation of other HVAC Systems. These points are:
INSTRUMENT NO. A P RELATIONSHIP OPDI-VC38 Control Room - Turbine Building OPDI-VC37A Control Room - Turbine Building OPDI-VC38D Train B Equipment Rm. - Misc. Elec. Equip.
Rm. Div. 21 Manometer Control Room - Lower Cable Spreading Room All readings were taken with the Control Room B train running and the corresponding emergency make-up air filtration unit operational.
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APPENDIX B STAIRWELL PRESSURIZATION
. Building tested included a thirteen story stairwell
. The stairwell pressurization flow rate was 8250 CFM
. Pressure measurements were made at each floor elevation
. Initial' corridor average pressure - 0.252" WC (63 Pa)
Minimum 0.24" WC Maximum 0.27" WC
. Pressure with two doors open (approximately. 42 FT') = 0.014" WC (3.4 Pa)
Minimum 0.01" WC Maximum 0.03" WC
Reference:
" Stairwell Pressuriztion" John Klote ASHRAE TRANSACTIONS LA-80-4 PP. 604-622
~
APPENDIX C UPPER CABLE SPREADING ROOM (UCSR) PRESSURE TEST TEST
-Pressure Reference A B C D Pressure in WC
' Control' Room /Turb. Bldg. 0.13" 0.13" 0.10" 0.06" UCSR/Turb. Bldg. 0.02" 0.04" 0.04" 0.01" UCSR/ Aux. Bldg. 0.05" 0.04" 0.03" 0.005" Across Door 0.01" 0.02" negligible negligible TESTS A. All doors closed - 4.5 ft.' penetration open B. - All doors closed - 4.5 f t.' penetration closed C. . One door open (16.3 ft.' open area)
D. Two doors open-(30'.4 ft.' open area): -
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9
. l TABLE 1 HISTORY OF BYRON CONTROL ROOM PRESSURE AVERAGE CON DIFFERENTIAI TEST DATE Inches W.C A- 10/12/84 0.04 B 12/05/84 0.08 C- 12/05/84 0.15 D 12/17/84 0.18
-- E 12/20/84 0.20
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