Application for Amends to Licenses NPF-37,NPF-66,NPF-77 & NPF-72,revising TS 3/4.7.4,3/4.7.4.1 & 3/4.7.4.2 for Byron & 3/4.7.4,3/4.7.4.1 & 3/4.7.2 for Braidwood,To Address Concerns of Generic Ltr 91-13 Re Esws Failures at SitesML20126F301 |
Person / Time |
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Site: |
Byron, Braidwood |
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Issue date: |
12/22/1992 |
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From: |
Simpkin T COMMONWEALTH EDISON CO. |
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To: |
Murley T NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
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Shared Package |
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ML20126F303 |
List: |
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References |
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GL-91-13, TAC-M73975, TAC-M73976, TAC-M81167, TAC-M81168, NUDOCS 9212300228 |
Download: ML20126F301 (7) |
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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
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 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 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 1999-07-30
[Table view] |
Text
U
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. * ( _ /1400 opus Placs
(
- j Downers orove, Illinois 60515 v December 22,1992 Dr. Thomas E. Murley, Director Office Of Nuclear Roactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555 Attn: Document Control Desk '
Subject:
Byron Station Units 1 and 2 Braldwood Station Units 1 and 2 Application for Amendment to Facility 03erating License NPF-37, NPF-66, NPF-72, and NPF 77 N 10 Docket.Nos. 50 45_4.A55.A56_anL457.
Reference:
TAC # M73975, M73976, M81167, M81168 :
Dear Dr. Murley:
Pursuant to 10 CFR 50.90, Commonwealth Edison (CECO) proposes to amend A mondix A, Technical Specification of Facility Operating License NPF-37, NPF-66 N PF 72 and NPF-77. The proposed amendmen; revises s aecifications 3/4.7.4,3/4.7.4.1, and 3/4.7.4.2 for Byron and 3/4.7.4 for Braldwooc . Also for Braidwood new specifications 3/4.7,4.1 and 3/4.7.4.2 are proposed. The purpose of-the revision is to address the concerns of Generic Letter 91-13 concerning Essential Service Water System failures at multi unit sites.
Detailed descriptions of the proposed changes at e presented in Attachments A and E. The revised Technical Specification pages are contained in Attachment B and F for Byron and Braidwood, respectively.
The proposed change has been reviewed and approved by both on site and :
off site review n accordance with CECO procedures. CECO has reviewed this.
proposed amendment in accordance with 10 CFR 50.92(c) and has determined that no L significant hazards consideration exists. These evaluations are documented in l Attachments C and G, Environmental Assessments have been completed and are.
l contained in Attachments D and H.
ZNLD/2382/1 i
I '921230022e 921222 4 {l DR ADOcK 0500
'b
4
^
Dr. Thomas E. Murley 2- December 22,1992
. CECO is notifying the State of Illinois by transmitting a copy of this letter and its attachments to the designated State Official, ,
To the best of my knowledge and belief the statements contained herein are true and correct. In some respects, these statements are not based on my personal knowledge but upon information received from other Commonwealth Edison and contractor empioyees. Such information has been reviewed in accordance with Company practice and I believe it to be reliable.
Please direct any questions regarding this matter to this office.
Respectfully, YWO) Terrence W. Simpkin Nuclear Licensing Administrator i
Attachment A: Byron Description of Proposed Changes Attachment B: Byron Marked Up Pages Attachment C: By_ron No Significant Hazards Consideration Attachment D: Byron Environmental Assessment Attachment E: Braidwood Description of Proposed Changes Attachment F: Braidwood Marked Up Pages _
Attachment G: Braidwood No Significant Hazards Consideration Attachment H: Braidwood Environmental Assessment cc: R. Elliott, Project Manager - NRR J. Hickman, Project Manager - NRR S. DuPont. Resident inspector - Braidwood W. Kropp, Resident inspector - Byron r /
iDocument1 Control Desk:- NRR Region ill Office I I " '( '
Office of Nuclear Facility Safety - IDNS //0LggGF - JJ _ g
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OFFICI AL SEAL MARYELLEN D.LONG NOTA 3Y FU2U151ME ^F ILL!NCS MY C;WlSU N E.GRES SnV93q.
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ZNLD/2382/2
ATTACHMENT A DESCRIPTION AND IMPACT OF PROPODED CHANGES DAQASIERnd In responso to Gonoric Letter 91-13, Byron reviewed the recommended Technical Specification and procedure improvements.
We concluded that the issues in the Lottor woro applicable to Byron and that we had previously adopted appropriate Technical Specifications to address the concern of Ensuntial Servico Water system (SX) failuros. In Commonwealth Edison's response to the Genoric Lottor, dated March 16 1992, Byron committed to mako refinomonts to the existing spe,cifications. Since thoro was no now information to support adopting the Specifications proposed in the Lotter, we chose to koop the specifications that the NRC-had already approved to address SX failures.
HMpparv of__the Proposed ChAngan A proposed change to 3.7.4 dolotos the two components of an Essential Service Water system. Surveillance requiroment 4.7.4.c is doloted (relocated). A proposed change to 3.7.4.1 clarifles when the specification is applicable. The proposed change to survoillanco 4.7.4.1 doos not specifically require that the Essential Service Water (SX) pump be crosstied. The proposed surveillanco also states that a flowpath is established or capable of being established; the specific valves required are doloted. An operator must be capablo of establishing this flow path and starting the availablo SX pump from the Main Control Room. Specification 3/4.7.4.2 is reworded for clarity. A discussion of the SX system crosatio is added to the Basos.
The marked up Technical Specification pages indicating the proposed changos are provided in Attachment D. A discussion of each change follows.
Dotalled Description of the Proposed Changig
- 1. Proposed changes to 3/4.7.4 e Current Requirement DescriptioD_And Dapes LCO 3.7.4 describes theofind th'opendent Essential Servico Water (SX) systems as having a loop and cooling tower.
Surveillanco requirement 4.7.4.c requires that the cooling tower fans be verified operable and that the cooling tower fill bo inspected. Those requirements ensure that the cooling tower operates as designed during an accident.
Rescription And1Dases of the Reauested Revision Byron previously proposed changes to Technical Specification 3/4.7.5 and the associated Bases to incorporate the results of the Ultimato lleat Sink (UHS) studios conducted for the Byron SX system. The proposed changes to 3/4.7.4 and 3/4.7.5 recognize that the cooling towers are part of the Ulis, which is a shared system The requirements for operability of the
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UHS are provided_in Specification 3/4.7.5. Specification:
3/4.7.4; currently _ includes requirements-for-the; cooling-towers and fans. The requirements'of SurveillanceJ4.7.4.c were duplicated in the proposed change.to 4.7.5 because they are more appropriate in-the UHS discussion. _Thearedundant -
-surveillance (4.7.4.c) is being deleted byLthis_ proposal. .
13Dact of the-ProDosed Chance _ _ _ ,
There are no changes to the requirementsfexcept for-the '
i numbering of the~ surveillance requirements. It,is more i appropriate to-include the cooling tower-fan operability.
requirements and cooling tower basin inspection requirements .
in the UHS Specification because they are not part of an independent system, as previously' described.
The proposed tms changes' move the requirements of Surveillance 4.7.4.c into-4.7.5.d and 4.7.5.j. Therefore,;to maintain the level of control, approval of'this (SX) amendment request is: contingent on approval of-the; UHS amendment request. There is no impact on"the safety: analyses as long as the requirements appear in either section.
- 2. Applicability of 3.7.4.1 DescriDtion and Bases of the Current Recuirement Specification 3.7.4.1 is applicable when Unit 2 (Unit 1) is_
in Modes 5 and'6, and Unit 1 (Unit 2) is in' Modes _1,-2, 3, and 4. This ensures that an SX-pump from a shutdown unit isL available'to support the operating. unit.
DescriDtion and Bases of the Recuested Revision-The proposed change reverses the order of the requirements to emphasize that the specification is to support the operating unit. .The proposed change adds that the specification is-applicable when there is no-fuel'in-the-reactor vessel.-'This 1s not a. defined mode in Table 1.2. ~The proposed bases change staten that the availability of"an SX pump in the shut' Gown unit ensares the availability of sufficient redundant-cooling. capacity for the operating unit. The shutidown condition-includes those times-wher. there is no--fuel in the
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reactor' vessel.
InDact of the ProDosed Chance The proposed change is more restrictive _than the existing requirement because-the:SX pump-must be available under an additional condition. It is important to include the condition when.the shut down unit has no fuel-in the reactor vessel because the specification isfwritten for.a shutDdown.
unit to support ~an operating unit. It makes no' difference whether there is fuel in--the shut down unit's reactor. Byron recognizes thisoand performs the surveillances when-the shut:
or when the unitEis defueled.
-down The enhancedunit is inLMode wording is 5 or?6,istent cons with Table 1.2 and ensures tthat'the shut down unit's SX pump will be available to support the operating unit.
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- 3. Proposed Changes to Surveillance 4.7.4.1 pescr:LDtion and Bases of the Current Recuirement Surven11ance 4.7.4.1 demonstrates availability of the SX pumps by starting the pumps and verifying crosstie capability is available to the opposito unit's system. The surveillance lists specific valves that-must be open or capable of being-opened to establish a flowpath. The surveillance lists which bus must be energized to supply power to the available SX pump. The surveillances ensure that an SX pump can supply water to the opposite unit.
Description and Bases of the Recuented Revision The purpose of proposed Surveillsace 4.7.4.1 is to demonstrate that the SX pump is available to support operation of the opposite unit. The reference-to the crosstic is deleted since it is addressed specifically in Specification 3/4.7.4.2.
The specific list of valves to be open or capable of being opened is replaced by-a requirement to have, or be able to establish, a flowpath.. It is still necessary to be able'to establish this flowpath from the Fain Control Room. The wording flowpath.
allows for operator flexibility in establishing the A new surveillance ensures that the available SX pump can be manually started from the Main Control Room. This requires several things, including energizing the bus, racking in the breaker, and having control powe: available. The new requirement, therefore, provides additional assurance that the SX pump will be able to perform its safety function because the surveillance is more inclusive.
A proposed editorial change replaces " day" with "24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />" to be consistent with Table 1.1 and other specifications.
Impact of the Proposed Chance The changes do not affect the system's ability to perform its safety function. The crosstie valves, ISX005 and 2SX005, are already covered in 3/4.7.4.2. The. proposed-changes to Surveillance 4.7.4.1.a allow alternate valves to be used in establishing a'flowpath. This does not affect any accident analyses because the flowpath.provided in the current surveillance is not specifically listed. As long as a flowpath exists, the analyses remain bounding.
An additional surveillance that-verifies that the SX pump can be started from the Main Control Room-assurance that the pump will function as provides additional designed. Merely having the bus energized does not guarantee that the pump can be started. A flowpath, control power and properly positioned breaker are also prerequisites to using the pump to supply cooling water. Requiring-that a pump be capable of being started from the Main Control Room includes all actions necessary to provide cooling water; therefore the pump would be capable of performing its safety function.
- 4. Editorial-changes to 3/4.7.4.2 '
Dascription and Bases of the current Requirement-Specification 3/4.7.4.2 is applicable in Modes 1, 2, 3, and
- 4. The crosatie serves as a flowpath between Units 1 and 2. l The crosstie valves, 1SX005 and 2SX005, are cycled or- !
verified locked open with power removed to ensure that flow l from one unit to the opposite unit can be established.
Description _and Bases of the Requested Revision The proposed change adds that.the LCO applies with any unit ;
in Modes 1, 2, 3, or 4, which is how Byron already performs the surveillance. The word change is for clarity.. The LCO has also been clarified requiring the valve to be open or capable of being open from the Main Control Room to provide an Essential Service Water flowpath between Unit 1 and Unit
- 2. This wording provides a more accurate description of the purpose of the crosstie valves.
The surveillance is clarified to state explicitly that M _
crosstle valve shall be cycled or verified locked open with power removed. An editorial change is proposed to replace
" verify" to " verifying the" to improve readability. The requirements themselves are not changed. The requirements ensure that the SX crosstic remains capable of providing flow from one unit to the other.
Ippact of the ProDosed Chance There are no changes to the requirements. These changes are editorial in nature and serve to improva readability. The-proposed wording changes more accurately reflect how this Technical Specification is applied, since there are no changes to the actions, there is no impact on the safety analyses involving the crosstie. In Commonwealth Edison's request for the original Technical Specification,-we-stated that the crosstic would be required whenever either or both units are in Modes 1, 2, 3, or 4. The SER issued with the amendment, dated Hovember-23, 1988, also noted this condition. The proposed wording change preserves this meaning.
- 5. Addition to Bases for 3/4.7.4 Description and Dases of the current Recuirement The Bases for 3/4.7.4 describes the safety function for the Essential Service Water (SX) system.
Description an_d Bases of the Recuested Revision The proposed change adds a sentence describing the SX system crosstie for redundant cooling capacity for two unit sites.
The sentence based on the Bases proposed in Generic Letter 91-13.
Impact of the Proposed chance The proposed Bases describe the SX crosstle, which the Generic Letter identifies as an important feature of Byron's design. To recognize the significance of the crosstie for
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providing redundant cooling capacity, the Bases are amended.
There are no' changes to plant operation resulting from the Bases change. Specification 3 requirements for the crosstie./4.7.4.2 provides the Schedule Recuirements There are no specific schedule requirements for the requested changes. However, deleting Surveillance 4.7.4.c., as discussed in item 1 above, is contingent upon approval of our proposed amendment to Technical Specification 3/4.7.5. Therefore, to ensure that controls are in place to verify cooling tower fan operability and that there is no abnormal breakage or degradation of the cooling tower fill material,.this request should-not be issued prior to issuing revisions to Specification 3/4.7.5.
Identification _and discussion of any irreversible consecuences The proposed changes are mostly editorial wording changes that support the current interpretations of the specifications. The-additional requirement enhances the availability of the SX pump to operate as designed. No irreversible consequences will result from the proposed changes.
Conclusion Based upon the information presented above, it can be concluded that the question. proposed changes do not constitute an unreviewed safety