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Category:OPERATING LICENSES & AMENDMENTS
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 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 ML20195D5081998-11-0404 November 1998 Errata to Amends 96 & 96 to Licenses NPF-72 & NPF-77, Respectively,Correcting TS Page 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 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 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 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 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 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 ML20134K7971997-02-12012 February 1997 Amends 85,85,77 & 77 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,eliminating License Conditions 2.C.(16),(6) & (5), Requiring Licensee to Conduct Addl Corrosion Testing of Sleeved SG Tubes ML20113D7601996-06-26026 June 1996 Amends 76 & 76 to Licenses NPF-72 & NPF-77,respectively, Revising TSs to Eliminate Periodic Response Time Testing Requirements for Selected Pressure & Differential Pressure Sensors in RTS ML20101R3861996-04-12012 April 1996 Amends 83,83,72 & 77 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Re Permitting SG Tubes Be Repaired Using Tig Welded Sleeve Process & Remove Ref to Kinetically Welded Sleeving Process ML20101R5451996-04-10010 April 1996 Amends 74 & 74 to Licenses NPF-72 & NPF-77,respectively, Revising TSs for Plant to Implement Ten of Line Item TS Improvements Included in GL 93-05, Line Item TSs Improvements to Reduce Surveillance Requirements.. ML20101Q5241996-04-0404 April 1996 Amends 73 to Licenses NPF-72 & NPF-77,revising TS to Replace Existing Scheduling Requirements for Overall Integrated & Local Containment Leakage Rate Testing W/Requirement to Perform Testing IAW 10CFR50,App J,Option B ML20101F1661996-03-15015 March 1996 Amends 72 to Licenses NPF-72 & NPF-77,revising Action Statements & Allowed Outage Time for Inoperability of One Channel & Both Channels of Source Range Neutron Flux Instrumentation in Shutdown Modes 3-5 ML20149L1961996-02-16016 February 1996 Amends 79 & 71 to Licenses NPF-37,NPF-66,NPF-72,NPF-77, Respectively,Revising TS 3/4.8.1 by Replacing Table 4.8-1, Diesel Generator Test Schedule & Deleting TS 4.8.1.1.3, Repts. Revs Consistent W/Guidance in GL 94-01 ML20095G6631995-12-19019 December 1995 Amends 78,78,70 & 70 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,to Allow Use of Alternate Zirconium Based Fuel Cladding,Zirlo & Permit Limited Substitution of Fuel Rods W/Zirlo Filler Rods ML20094E5441995-11-0202 November 1995 Amends 76,76,86 & 86 to Licenses NPF-37,NPF-66,NPF-72 & NPF- 77,respectively.Amends Change TS 3/4.6.1.7,CP Ventilation Sys,To Allow Simultaneous Opening of 8-inch Miniflow Purge Supply & Evs ML20085N1971995-06-22022 June 1995 Amends 72,72,63 & 63 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Re Repair Criteria for Defects Found in SG Tubes ML20081G5941995-03-20020 March 1995 Amends 71,71,62 & 62 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,adding New Requirements to TS to Ensure Essential Service Water Sys Pump & Crossover Path Available from Shutdown Unit as Backup to Operating Unit ML20080N2881995-03-0303 March 1995 Amends 70,70,61 & 61 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TSs to Increase AOT for Inoperable CR Chiller ML20080N4651995-02-28028 February 1995 Amends 60 & 60 to Licenses NPF-72 & NPF-77,respectively, Changing Plant TS to Remove Requirement to Verify,Every 18 Months,That Control Room Ventilation Can Be Manually Isolated ML20078C3001995-01-20020 January 1995 Amends 68,68,58 & 58 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,approving Use & Storage in Spent Fuel Racks of Fuel W/Enrichment Not to Exceed Nominal 5.0 Weight Percent U-235 ML20080F3961995-01-0606 January 1995 Amends 67,67,57 & 57 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS to Lower SG Primary to Secondary Leakage Rate Limit,Increase Sample Size for Inservice Insp of SG Tube Sleave & Adds Corrosion Insp ML20078P9471994-12-16016 December 1994 Reformatted TS Pp 3/4 4-17,3/4 4-17a,B 3/4 4-3 & B 3/4 4-3a to Amends 55 & 54 to Licenses NPF-72 & NPF-77,respectively. Reformated Pp Issued to Enable Licensee to Codify TS Book ML20078C2231994-10-21021 October 1994 Amends 65,65,56 & 55 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,changing TS to Reflect Reduced Thermal Flow to Compensate for Increased SG Tube Plugging Up to 15 Percent of Total Number of Tubes ML20073G3291994-09-29029 September 1994 Amends 64,64,55 & 54 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,removing Specific Vendor Technical Rept References ML20072G9671994-08-18018 August 1994 Amend 54 to License NPF-72,re Changes to TS to Add SR Related to Plant Specific Insp Guidelines to Section 4.4.5.4.a(11) ML20071F4341994-06-30030 June 1994 Amends 62,62,52 & 52 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,changing TS 4.6.1.2, Containment Leakage, by Removing Specific Requirement That Containment Type a Leak Testing Be Performed as Stated ML20069G9351994-05-24024 May 1994 Corrections to Amend 50 to License NPF-72,re TSs Pages 3/4 4-13,3/4 4-15,3/4 4-18 & 3/4 4-19.Pages Were Submitted for Clarification Only & Amend Number Should Not Have Been Referenced ML20029E6051994-05-16016 May 1994 Amend 51 to License NPF-77 Changing TS by Adding Note Which Relieves Plant from Compliance W/Provisions of TS 4.0.4 ML20070Q2311994-05-0707 May 1994 Amend 50 to License NPF-72,revising TS 4.4.5.2,4.4.5.4 & 4.4.5.5 to Allow Usage of voltage-based Steam Generator Tube Plugging Criteria for Defects Located at Tube Support Plate Elevations ML20064H5461994-03-11011 March 1994 Amends 60,60,48 & 48 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Requirements for Snubber Visual Insp Intervals & Corrective Actions in Accordance W/Gl 90-09 ML20064C5171994-03-0404 March 1994 Amends 47,47,59 & 59 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS to Allow Replacement of 125 Volt DC Gould Batteries W/New 125 Volt DC At&T Batteries & Rephrase Specifications for Design Duty Cycle ML20063M2641994-03-0404 March 1994 Amends 58,58,46,& 46 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS 3/4.4.5, SG, to Allow Sleeving of Defective SG Tubes as Alternative to Tube Plugging.Reissued 940308 ML20064D6351994-03-0404 March 1994 Amends 59 to Licenses NPF-37 & NPF-66 & Amends 47 to Licenses NPF-72 & NPF-77,respectively,revising TSs to Allow Replacement of 125 Volt DC Gould Batteries W/New 125 Volt Dc At&T Batteries & Rephrasing Specification ML20063M0971994-03-0404 March 1994 Amends 46,46,58 & 58 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revise TS 3/4.4.5,SG to Allow Sleeving of Defective SG Tubes as Alternative to Tube Plugging 1999-09-08
[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
. _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
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UNITED STATES p
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NUCLEAR REGULATORY COMMISSION o
WASHINGTON. D.C. 2006H1001
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BRAIDWOOD STATION. UNIT NO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 14,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Par 151 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No NPF-72 is hereby amended to read as follows:
i 9808260192 980818 DR ADOCK 05000456 p
PDR
2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 94 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Stewart N. Bailey, Pr
- Ma ger Project Directora?.e 1 -
Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 18, 1998 l
f
ll UNITED STATES p
S NUCLEAR REGULATORY COMMISSION E
I WASHINGTON, D.C. 30seH001
\\...../
COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 94 License No. NPF-77 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated January 14,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) j that such activities will be conducted in compliance with the Commission's j
regulations; 1
D.
The issuance of this amendment will not be inimical to the common defense and i
security or to the health and safety of the public; and
)
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
I 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-77 is hereby amended to read as follows:
I l
2-(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 94 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental l
Protection Plan.
3.
This license amendment is effective as of the date ifits issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION i
Stewart N. Bailey, Proj tM r
Project Directorate Ill-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: August 18, 1998 l
l I
l l
l l
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ELECTRICAL POWER SYSTEMS 3/4.8.2 D.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 As a minimum the following D.C. electrical sources shall be OPERABLE:
a.
125-Volt D.C. Bus 111 fed from Battery 111 for Unit 1 (Bus 211 fed from Battery 211 for Unit i
- 2) and its associated full capacity charger, and with one of its associated crosstie breakers in the open position, and b.
125-Volt D.C. Bus 112 fed from Battery 112 for Unit 1 (Bus 212 fed from Battery 212 for Unit
- 2) and its associated full capacity charger, and with one of its associated crosstie breakers i
in the open position.
APPLICABILITY: MODES 1,2, 3, and 4.
ACTION:
a.
With one of the required 125-Volt D.C. buses inoperable due to its normal associated full capacity charger being inoperable, operations may continue provided that within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> the inoperable bus and its associated battery are energized by the opposite unit's 125-Volt D.C.
bus and its OPERABLE charger via the crosstie breakers and that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the inoperable bus and its charger are restored to OPERABLE status. Otherwise be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
b.
With both of the crosstie breakers closed for a 125-Volt D.C. bus that is required to be OPERABLE and with both units operating (Modes 1,2,3, or 4), the 125-Volt D.C. bus may energize the opposite unit's inoperable 125-Volt D.C. bus having an inoperable charger without a load restriction.
c.
With both of the crosstie breakers closed for a 125-Volt D.C. bus that is required to be OPERABLE and with the opposite unit shutdown (ded items 1 and 2 below are satisfied.
Modes 5,6, or defueled), the crosstie breakers may remain closed for up to 7 days provi Otherwise open one of the crosstie breakers.
(1)
The shutdown unit's bus load is restricted to:
Shutdown Unit Operating Unit Load Batterv Status Batterv Tvoe Restriction noperable AT&T 100 Amps Inoperable C&D 200 Amps l
OPERABLE Either None (2)
If a load restriction applies, then once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that the shutdown unit's bus loading will not exceed the load restriction.
d.
With one of the required 125 Volt D.C. buses inoperable, except for the allowances of l
ACTIONS (a), (b), or (c) above, restore the inoperable bus to OPERABLE status within 2 l
hours or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
SURVEILLANCE REQUIREMENTS 4.8.2.1.1 Each D.C. bus shall be determined OPERABLE and energized from its battery at least j
once per 7 days by verifying correct breaker alignment.
l BRAIDWOOD-UNITS 1 & 2 3/4 8-10 AMENDMENT NO. 94
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 4.8.2.1.2 Each 125-volt battery bank and its associated charger shall be demonstrated OPERABLE:
a.
At least once per 7 days by verifying that:
1)
The parameters in Table 4.8-2 meet the Category A limits, and 2)
The total battery terminal voltage is greater than or equal to 130.5 volts (AT&T) 127.6 volts (C & D) on float charge.
l b.
At least once per 92 days and within 7 days after a batte disch'arge with battery terminal voltage below 110 volts, or battery overcharge th battery terminal voltage
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above 145 volts, by verifying that:
1 1)
The parameters in Table 4.8-2 rneet the Category B limits, 2)
There is no visible corrosion at either terminals or connectors, or the connection resistance of these items is less than 4
150 x 10 ohm *, and 3)
The average electrolyte temperature of all connected cells is above 60*F.
c.
At least once per 16 months by verifying that:
1)
The cells, cell plates, and battery racks show no visual indication of physical
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damage or abnormal deterioration,
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2)
The cell-to-cell and terminal connections are clean, tight, and coated with anticorrosion material, 3)
The resistance of each cell-to-cell and terminal connectio'n is less than or equal 4
to 150 x 10 ohm *, and 4)
The battery charger will supply a load equal to the manufacturer's rating for at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
d.
At least once per 18 months, during shutdown, by verifying that the battery capacity is adequate to supply and maintain in OPERABLE status all of the actual or s,imulated i
emergency loads for the design duty cycle when the battery is subject to a battery
]
service test; l
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- Obtained by subtracting the normal resistance of: 1) the cross room rack connector (C & D only:
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400 x 10 ohm, typical) and 2) the bi-level rack connector (both AT&T and C & D: 50 x 10 ohm, typical); from the measured cell-to-cell connection resistance.
l BRAIDWOOD - UNITS 1 & 2 3/4 6-11 AMENDMENT NO. 94 l
ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) e.
At least once per 60 months, during shutdown, by verifying that the battery capacity is i
at least 95% (AT&T) 80% (C & D) of the manufacturer's rating when subjected to a p
i performance discharge test or a modified performance discharge test. The modified 4
performance discharge test and the performance discharge test may be performed in l
l h,eu of the battery service test required by Specification 4.8.2.1.2d.;
f.
At least once per 12 months
- during shutdown, by giving performance discharge tests or modified performance discharge tests of battery capacity to any battery that shows signs of degradation or has reached 85% of the service life expected for the application. Degradation is indicated when the battery capacity drops more than 5% (AT&T) 10% (C & D) of rated capacity from its capacity on the previous l
performance test o modified performance test, or is below 100% (AT&T) 90%
(C & D) of the manufacturer's rating.
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- Testing at a 2 year interval is acceptable as long as the battery capacity is greater than 100% of
_ rated capacity and the battery shows no signs of degradation.
BRAIDWOOD-UNITS 1 & 2 3/4 8-11 a AMENDMENT NO. 94 1
TA_BLE 4.8-2 (C & D)
BATTERY SURVEILLANCE REQUIREMENTS l
CATEGORY AN CATEGORY BS PARAMETER LIMITS FOR EACH LIMITS FOR cACH ALLOWABLE
- l DESIGNATED PILOT CONNECTED CELL VALUE FOR EACH
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CELL CONNECTED CELL j
Electrolyte
> Minimum level
> Minimum level Above top of Level indication mark, indication mark,
- plates, and < %" above and < %" above and not maximum level maximum level overflowing indication mark indication mark Float Volteys 12.13 volts t 2.13 volts *
> 2.07 volts Not more than 0.020 below I
the average of all connected Specific
> 1,195 cells W
Gravity A 1.200*
Average of all Average of all connected cells connected cells
> 1.205 1 1.195*
TABLE NOTATIONS l
(1) For any Category A parameter (s) outside the limit (s) shown, the battery may be considered OPERABLE prov,ded that within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> all the Category B measurements are taken and i
found to be within their allowable values, and provided all Category A and B pararneter(s) are restored to within limits within the next 6 days.
(2) OPERABLE prov,ded that the Category B parameters are within their allowable values an i
provided the Category B parameter (s) are restored to within limits within 7 days.
l (3) Any Category B parameter not within its allowable value indicates an inoperable battery.
I4) Corrected for electrolyte temperature.
(5) Or battery charging current is less than 3 amps when on charge.
(6) Corrected for average electrolyte temperature.
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l BRAIDWOOD-UNITS 1 & 2 3/4 8-12a AMENDMENT NO. 94
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ELECTRICAL POWER SYSTEMS D C. SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION j
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3.8.2.2 As a minimum, one 125-volt D.C. bus fed from its battery and its associated full-capacity charger and with one of its associated crosstie breakers in the open position shall be OPERABLE.
APPLICABILITY: MODES 5 and 6.
ACTION:
)
a.
With.both of the crossile breakers closed for the 125 Volt D.C. bus that is required to be OPERABLE and with the opposite unit operating (Modes 1,2,3, or 4), the shutdown unit's operable 125-Volt D.C. bus may energize the operating unit's inoperable 125-Volt D.C. bus having an inoperable charger without a load restriction.
b.
With both of the crosstie breakers closed for the 125-Volt D.C. bus that is required to be OPERABLE and with both units shutdown (Modes 5,6, or defueled), the 125-Volt D.C. bus may energize the opposite unit's 125-Volt D.C. bus for up to 7 days provided items 1 and 2 below are satisfied. Otherwise open one of the crosstie breakers.
(1)
The opposite unit's bus load is restricted to:
Opposite Bus Operable Bus Loao Battery Status Battery Tvoe Restrictica inoperable AT&T 100 Amps inoperable C&D 200 Amps OPERABLE Either None (2)
If a load restriction applies, then once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> verify that the opposite shutdown unit's bus loading will not exceed the load restriction.
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c.
With the required 125-Volt D.C. bus inoperable, except for the allowances of ACTIONS (a) l or (b) above, immediately suspend all operations involving CORE ALTERATIONS, positive I
reactivity additions, or movement of irradiated fuel; initiate corrective action to restore the required bus to OPERABLE status as soon as possible; and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, depressurize and vent the Reactor Coolant System through at least a 2 square inch vent.
SURVEILLANCE REQUIREMENTS 4.8.2.2 The above required 125-volt D.C. bus fed from its battery and its associated charger shall be demonstrated OPERABLE per Specifications 4.8.2.1.1 and 4.8.2.1.2.
l BRAIDWOOD - UNITS 1 & 2 3/4 6-13 AMENDMENT NO. 94
ELECTRIC POWER SYSTEMS BASES A.C. SOURCES. D.C. SOURCES. ANC',,qiplTE POWER DISTRIBUTION (Continued)
The Surveillance Requirement for demonstrating the OPERABILITY of the station batteries is based on the recommendations of Regulatory Guide 1.129," Maintenance Testing and Replacement of Large Lead Storage Batteries for Nuclear Power Plants," February 1978, and IEEE Std 450-1980,,,IEEE Recommended Practice for Maintenance, Testing, and Replacement of
' Large Lead Storage Batteries for Generating Stations end Substations."
The modified performance discharge test is described in IEEE Std 450-1995, "lEEE l
d Recommended Practice for Maintenance, Testing and Replacement of Vented Lead-Acid Batteries for Stationary Applications." It is permissible to perform a modified performance discharge test on the battery in lieu of a service test and a performance discharge test as required l
. by Regulatory Guide'1.129, Regulatory l osition C.1, because the test discharge rate envelopes the load cycle of the service test.
Verification of the crosstie loading limits in Specifications 3.8.2.1 and 3.8.2.2 ensures that the OPERABLE battery will have sufficient capacity to energize the design basis loads of its DC bus while maintaining the limited DC loads of the inoperable DC bus on a shutdown unit.
Verifying average electrolyte temperature above the minimum for which the battery was sized, total battery terminal voltage on float charge, and the performance of battery service and discharge tests ensures the effectiveness of the charging system, the ability to handle high discharge rates and compares the battery capacity at that time with the rated capacity.
The battery service test is a special test of battery capability, as-found, to satisfy the design requirements (battery duty cycle) of the D.C. electrical power system. The discharge rate and length of the battery service test corresponds to the design duty cycle requirements as specified in UFSAR Subsection 8.3.2.1.1.
Table 4.8-2 specifies the normal limits for each designated pilot cell and each connected cell for electrolyte level, float voltage and specific gravity. The limits for the designated pilot cells i
j float voltage and specific gravity, greater than 2.18 volts (AT&T) 2.13 volts (C & D) and 0.015 l
below the manufacturers full charge specific gravity or a battery charger current that had stabilized at a low value, is characteristic of a charged cell with adequate capacity. The normal limits for each connected cell for float voltage and specific gravity, greater than 2.18 volts (AT&T) 2.13 volts (C & D) and not more than 0.020 below the manufacturers full charge specific gravity l
with an average specific gravity of all the connected cells not more than 0.010 Delow the manufacturers full charge specific gravity, ensures the OPERABILITY and capability of the battery.
Operation with a battery cell's parameter outside the normal limit but within the allowable value specified in Table 4.8-2 is permitted for up to 7 days. During this 7-day period: (1) the allowable values for electrolyte level ensures no physical damage to the plates with an adequate electron transfer capability; (2) the allowable value for the average specific gravity of all the cells, not more than 0.020 below the manufacturers recommended full charge specific ravity, ensures that the decrease in rating will be less than the safety margin provided in sizing; ( the allowable value for an individual cell's specific gravity, ensures that an individual cell's spect e gravity will not be more than 0.040 below the manufacturers full charge specific gravity and that the overall capability of the battery will be maintained within an acceptable limit; and (4) the allowable value for an individual cell's float voltage, greater than 2.14 volts (AT&T) 2.07 volts (C & D), ensures the l
battery's capability to perform its design function.
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I BRAIDWOOD-UNITS 1 & 2 B 3/4 8-2 AMENDMENT NO. 94
ATTACHMENT TO LICENSE AMENDMENT NOS. 94 AND 94 E6.Q1LITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-456 AND STN 50-457 l
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
Remove Paoes insert Paoes 3/4 8-10 3/4 8-10 3/4 8-11 3/4 8-11 3/4 8-11a 3/4 8-11a 3/4 8-12a 3/4 8-12a 3/4 8-13 3/4 8-13 8 3/4 8-2 B 3/4 8-2
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