|
---|
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 ML20212A6801999-09-0909 September 1999 Corrected Tech Spec Pages 4 to Amends 110 & 110 to Licenses NPF-37 & NPF-66,correcting License Conditions 2.C(17) & 2.C(6) ML20212A8121999-09-0808 September 1999 Amends 103 & 103 to Licenses NPF-72 & NPF-77,respectively, Changing Max Allowable Temp of UHS in TSs from 98 Degrees F to 100 Degrees F ML20211A8071999-08-10010 August 1999 Amends 110 & 110 to Licenses NPF-37 & NPF-66,respectively, Deleting License Conditions Which Have Been Satisfied, Revising Others to Delete Parts No Longer Applicable or to Revise References & Making Editorial Changes ML20207F1181999-06-0202 June 1999 Amend 102 to Licenses NPF-72 & NPF-77,revising TS 3.9.3 Re Use of Gamma-Metrics post-accident Source Range Neutron Flux Monitors as Alternative to Westinghouse Source Range Neutron Flux Monitors During Mode 6 Operations (Refueling) ML20206G5961999-05-0303 May 1999 Amends 108,108,101 & 101 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Requirements for Spent Fuel Pool Inadvertent Draindown Elevation ML20206B5451999-04-23023 April 1999 Amends 107 & 107 to Licenses NPF-37 & NPF-66,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & ESFAS ML20206B6841999-04-23023 April 1999 Amends 100 & 100 to Licenses NFP-72 & NPF-77,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & Efsas ML20205D6511999-03-26026 March 1999 Amends 99 to Licenses NPF-72 & NPF-77,respectively,changing TS to Support Online Replacement of Vital Batteries 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 ML20248E0221998-05-26026 May 1998 Amends 103 & 103 to Licenses NPF-37 & NPF-66,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Govern Valves from Monthly to Quarterly ML20216C1161998-05-0808 May 1998 Amends 102 & 102 to Licenses NPF-37 & NPF-66,respectively, Deferring Next Scheduled Type a Containment Integrated Leak Rate Test for Plant,Unit 2,until Next Refueling Outage in 1999 ML20203B7231998-02-0303 February 1998 Amends 92 & 92 to Licenses NPF-72 & NPF-77,respectively, Revise TS to Reflect Forthcoming Replacement of Original Steam Generators ML20203A2751998-02-0303 February 1998 Amends 101 & 101 to Licenses NPF-37 & NPF-66,respectively, Reflect Forthcoming Replacement of Original Steam Generators ML20199E6871998-01-29029 January 1998 Amends 99,99,90 & 90 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TSs to Update Containment Vessel Structural Integrity to Meet Provisions of Recent Rev to 10CFR50.55a ML20199K4681998-01-23023 January 1998 Amends 89 & 89 to Licenses NPF-72 & NPF-77,respectively, Relocating RCS Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & Associated LTOP Sys Setpoint Curves ML20199J0281998-01-23023 January 1998 Amends 98 & 98 to Licenses NPF-37 & NPF-66,respectively, Relocating,Rcs Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & LTOP Sys Setpoint Curves ML20199F3631998-01-22022 January 1998 Amends 97 & 97 to Licenses NPF-37 & NPF-66,respectively. Amends Revise TS & Associated Bases Re Primary Containment Pressure & Reactor Coolant Sys Volume ML20199H7861998-01-22022 January 1998 Amends 88 & 88 to Licenses NPF-72 & NPF-77,respectively, Revising TS & Associated Bases Re Primary Containment Pressure & RCS Vol ML20199C1651998-01-15015 January 1998 Amends 96 & 96 to Licenses NPF-37 & NPF-66,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement at Plant 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 ML20198H7521997-12-29029 December 1997 Errata to Amend 94 & 94 to Licenses NPF-37 & NPF-66, Correcting Typo That Was Inadvertently Introduced on TS Page 5-5 ML20198B5691997-12-12012 December 1997 Amends 95 & 95 to Licenses NPF-37 & NPF-66,respectively, Changing TS 3/4.7.5, UHS & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations 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 ML20203D3581997-12-0404 December 1997 Amends 94 & 94 to Licenses NPF-37 & NPF-66,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20202E5711997-11-25025 November 1997 Amends 93 & 93 to Licenses NPF-37 & NPF-66,respectively, Revising TS to Permit Installation & Use of C&D Charter Power Sys,Inc,Batteries 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 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 ML20210K4051997-08-13013 August 1997 Amends 92 & 92 to Licenses NPF-37 & NPF-66,respectively, Authorizing Change to Realistic Dose Values for Process Gas Sys Rupture in Section 15.0 of Plant UFSAR ML20210K7021997-08-13013 August 1997 Amend 91 to License NPF-66,revising TS 4.5.2.b.1 to Clarify That Venting Only Required on ECCS Subsystems That Are Idle or Stagnant 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 ML20148F6661997-06-0101 June 1997 Amend 90 to License NPF-37,revises TS 4.5.2.b.1 to Include Use of UT to Verify That ECCS Completely Filled W/Water 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 ML20137X0781997-04-16016 April 1997 Amends 88 to Licenses NPF-37 & NPF-66,respectively, Relocating Certain cycle-specific Parameter Limits from TSs to Operating Limits Rept 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 ML20137L4761997-04-0202 April 1997 Amends 86 & 86 to Licenses NPF-37 & NPF-66,respectively, Allowing Util to Take Credit,On Temporary Basis,For Soluble Boron in Spent Fuel Storage Pool Water in Maintaining Acceptable Margin of Subcriticality 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 ML20113C2201996-06-26026 June 1996 Amends 84 & 84 to Licenses NPF-37,NPF-66,respectively, Modifying TSs to Eliminate Periodic Response Time Testing Requirements for Selected Pressure & Differential Pressure Sensors in RTS 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 ML20101S2241996-04-16016 April 1996 Corrected Amends 81 to Licenses NPF-37 & NPF-66, Respectively 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.. ML20101R5291996-04-10010 April 1996 Amends 82 & 82 to Licenses NPF-37 & NPF-66,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.. ML20101Q0901996-04-0404 April 1996 Amends 81 to Licenses NPF-37 & NPF-66,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 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 1999-09-09
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20217N3631999-10-13013 October 1999 Amends 111,111,104 & 104 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Requirements Related to cross- Tie DC Power Buses Between Units & Removing Refs to At&T Batteries Which Have Been Replaced at Braidwood Station ML20212A6801999-09-0909 September 1999 Corrected Tech Spec Pages 4 to Amends 110 & 110 to Licenses NPF-37 & NPF-66,correcting License Conditions 2.C(17) & 2.C(6) ML20212A8121999-09-0808 September 1999 Amends 103 & 103 to Licenses NPF-72 & NPF-77,respectively, Changing Max Allowable Temp of UHS in TSs from 98 Degrees F to 100 Degrees F ML20211A8071999-08-10010 August 1999 Amends 110 & 110 to Licenses NPF-37 & NPF-66,respectively, Deleting License Conditions Which Have Been Satisfied, Revising Others to Delete Parts No Longer Applicable or to Revise References & Making Editorial Changes ML20210J1711999-07-30030 July 1999 Application for Amends to Licenses NPF-72 & NPF-77,proposing Temporary Changes to TS Re Upper Temperature Limit for Ultimate Heat Sink ML20209B7301999-06-30030 June 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,providing Correction to LCO Associated with TS Section 3.8.5, DC Sources - Shutdown & Deleting Various References to At&T Batteries in Braidwood TS Section 3.8 ML20207F1181999-06-0202 June 1999 Amend 102 to Licenses NPF-72 & NPF-77,revising TS 3.9.3 Re Use of Gamma-Metrics post-accident Source Range Neutron Flux Monitors as Alternative to Westinghouse Source Range Neutron Flux Monitors During Mode 6 Operations (Refueling) ML20206G5961999-05-0303 May 1999 Amends 108,108,101 & 101 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Requirements for Spent Fuel Pool Inadvertent Draindown Elevation ML20206B5451999-04-23023 April 1999 Amends 107 & 107 to Licenses NPF-37 & NPF-66,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & ESFAS ML20206B6841999-04-23023 April 1999 Amends 100 & 100 to Licenses NFP-72 & NPF-77,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & Efsas ML20205D6511999-03-26026 March 1999 Amends 99 to Licenses NPF-72 & NPF-77,respectively,changing TS to Support Online Replacement of Vital Batteries ML20204H9661999-03-23023 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TSs to Support Installation of New Boral high-density SFP Storage racks.Non-proprietary & Proprietary Info Encl.Proprietary Info Withheld.Per 10CFR2.790 ML20204H4211999-03-22022 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20198N3351998-12-29029 December 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Twelve RTS & ESFAS Allowable Values Contained in ITS Table 3.3.1-1 & Table 3.3.2-1 ML20196B3941998-11-25025 November 1998 Application for Amends to Licenses NPF-72 & NPF-77, Facilitating Replacement of 125 Vdc At&T Batteries with New 125 Vdc C&D Batteries While in Mode 1-4 ML20195J4101998-11-19019 November 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising App C,Addl License Conditions,By Deleting & Adding License Conditions as Stated.Marked Up App C Pages, Encl ML20195D5081998-11-0404 November 1998 Errata to Amends 96 & 96 to Licenses NPF-72 & NPF-77, Respectively,Correcting TS Page ML20155H9941998-10-30030 October 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Design Features Description Contained in Section 5.6.2 ML20154P1571998-10-15015 October 1998 Amends 97 & 97 to Licenses NPF-72 & NPF-77,respectively, Revising TS Re non-accessible Area Exhaust Filter Plenum Ventilation Sys to Reflect Design Lineup ML20151T2001998-09-0303 September 1998 Amends 95 & 95 to Licenses NPF-72 & NPF-77,respectively, Changing TS Limits on RCS Dei ML20237D4471998-08-18018 August 1998 Amends 94 & 94 to Licenses NPF-72 & NPF-77,respectively, Revising TS to Support Replacement of 125 Volt Direct Current At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries ML20248C5301998-05-29029 May 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Bases Section 3/4.4.4, Relief Valves to Credit Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS ML20248F4521998-05-26026 May 1998 Amends 93 & 93 to Licenses NPF-72 & NPF-77,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Governor Valves from Monthly to Quarterly ML20248E0221998-05-26026 May 1998 Amends 103 & 103 to Licenses NPF-37 & NPF-66,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Govern Valves from Monthly to Quarterly ML20216C1161998-05-0808 May 1998 Amends 102 & 102 to Licenses NPF-37 & NPF-66,respectively, Deferring Next Scheduled Type a Containment Integrated Leak Rate Test for Plant,Unit 2,until Next Refueling Outage in 1999 ML20217E1771998-03-24024 March 1998 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Surveillance Sections & Bases to Allow Util to Defer 10CFR50,App J Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20203B7231998-02-0303 February 1998 Amends 92 & 92 to Licenses NPF-72 & NPF-77,respectively, Revise TS to Reflect Forthcoming Replacement of Original Steam Generators ML20203A2751998-02-0303 February 1998 Amends 101 & 101 to Licenses NPF-37 & NPF-66,respectively, Reflect Forthcoming Replacement of Original Steam Generators ML20199E6871998-01-29029 January 1998 Amends 99,99,90 & 90 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TSs to Update Containment Vessel Structural Integrity to Meet Provisions of Recent Rev to 10CFR50.55a ML20199K4681998-01-23023 January 1998 Amends 89 & 89 to Licenses NPF-72 & NPF-77,respectively, Relocating RCS Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & Associated LTOP Sys Setpoint Curves ML20199J0281998-01-23023 January 1998 Amends 98 & 98 to Licenses NPF-37 & NPF-66,respectively, Relocating,Rcs Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & LTOP Sys Setpoint Curves ML20199F3631998-01-22022 January 1998 Amends 97 & 97 to Licenses NPF-37 & NPF-66,respectively. Amends Revise TS & Associated Bases Re Primary Containment Pressure & Reactor Coolant Sys Volume ML20199H7861998-01-22022 January 1998 Amends 88 & 88 to Licenses NPF-72 & NPF-77,respectively, Revising TS & Associated Bases Re Primary Containment Pressure & RCS Vol ML20199D2441998-01-15015 January 1998 Amends 87 & 87 to Licenses NPF-72 & NPF-77,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement ML20199C1651998-01-15015 January 1998 Amends 96 & 96 to Licenses NPF-37 & NPF-66,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement at Plant ML20198L8701998-01-14014 January 1998 Application for Amends to Licenses NPF-72 & NPF-77, Respectively.Proposed Amends Revise TS Section 3/4.8.2 & Bases,To Allow Replacement of 125 Volt Dc At&T Batteries W/New Charter Power Sys,Inc (C&D) Batteries ML20198L7981998-01-14014 January 1998 Application for Amends to Licenses NPF-72 & NPF-77, Revising TS to Reduce Dose Equivalent I-131 Activity from Requested 0.1 Microcuries/Gram to 0.05 Based on Revised Total end-of-cycle 7 Projected Leak Rate Value ML20198C2961997-12-30030 December 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.7.1.3, Condensate Storage Tank & Associated Bases for Plants to Raise Min Allowable CST Level ML20198H7521997-12-29029 December 1997 Errata to Amend 94 & 94 to Licenses NPF-37 & NPF-66, Correcting Typo That Was Inadvertently Introduced on TS Page 5-5 ML20198B5691997-12-12012 December 1997 Amends 95 & 95 to Licenses NPF-37 & NPF-66,respectively, Changing TS 3/4.7.5, UHS & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20203D3581997-12-0404 December 1997 Amends 94 & 94 to Licenses NPF-37 & NPF-66,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20203F6511997-12-0404 December 1997 Amends 86 & 86 to Licenses NPF-72 & NPF-77,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20202E5711997-11-25025 November 1997 Amends 93 & 93 to Licenses NPF-37 & NPF-66,respectively, Revising TS to Permit Installation & Use of C&D Charter Power Sys,Inc,Batteries ML20199A4651997-11-0707 November 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively.Amends Would Revise TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.b & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20198J9301997-10-16016 October 1997 Application for Amend to License NPF-37,requesting Exemption from Requirements of 10CFR70.24(a), Criticality Accident Requirements. Request Is Being Docketed to Reflect Units 1 & 2 So That Amend Numbers Remain Identical ML20202F4481997-10-10010 October 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Convert Byron & Braidwood Current Tech Specs to Byron & Braidwood Improved Tech Specs ML20211D9341997-09-24024 September 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Allowable Time Interval for Performing Turbine Throttle valve.Non-proprietary & Proprietary Trs,Encl.Proprietary Info Withheld ML20216G8341997-09-0808 September 1997 Application for Amend to TS 4.5.2.b & Associated Bases to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,to Bring Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20216F1141997-09-0202 September 1997 Application for Amends to Licenses NPF-72 & NPF-77,revising TS Section 3.4.8, Specific Activity. Rev 0 to Calculation BRW-97-0798-M & Rev 3 to Calculation 95-011 Encl ML20210K7021997-08-13013 August 1997 Amend 91 to License NPF-66,revising TS 4.5.2.b.1 to Clarify That Venting Only Required on ECCS Subsystems That Are Idle or Stagnant 1999-09-09
[Table view] |
Text
..
l
.e 1
pun p
t UNITED STATES s
j NUCLEAR REGULATORY COMMISSION 2
WASHINGTON, D.C. 20666-0001 4
0 9....
4 COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-456 BENDP'qOD STATION. UNIT NO.1 AMENDMEN i O FACILITY OPERATING LICENSE Amendment No. 97 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 August 23,1996, 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 tne activities authorized by this amendment can be conducted without endangering the healin 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 Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the licensu 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:
9810220233 981015 PDR ADOCK 05000454 P
PDR l
4.*
e 2
(2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 97 - 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 amendmerit is effective as of the date of its issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION Stewart N. Bailey, c'e ager Project Directorate 1-2 Division of Reactor Projects -lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: October 15, 1998 i
i i
9
ath 4
UNITED STATES f
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2006H00)
$[.....,$
l COMMONWEALTH EDISON COMPANY l
DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE l
Amendment No.97 License No. NPF-77 l
l 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated August 23,1996, complies with the standards and requirements I
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 tv sctivities authorized by this l
amendment can be conducted without endangering the health and safety of the i
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 Part 51 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-77 is hereby amended to read as follows:
a l !
(2)
Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 97 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 i
Protection Plan.
3.
This license amendment is effective as of the date if its issuance and shall be implement J within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION l
\\
l.
Stewart N. Bailey, Proj iana_
Project Directorate 111-2 Division of Reactor Projects - Ill/lV Office of Nuclear Reactor Regulation 1
Attachment:
1 Changes to the Technical Specifications l
Date of issuance: October 15, 1998 l
4
)
4 L
x +
l ATTACHMENT TO LICENSE AMENDMENT NOS. 97 AND 97 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 l-DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and contain verticallines indicating the area of change. Pages indicated by an asterisk are provided for convenience only.
Remove Papes insert Paaes 3/4 7-17 3/4 7-17
- 3/4 7-18 B 3/4 74 B 3/4 74 l
l l
l 9
l i
i i
4 l
s o PLANT SYSTEMS 3/4.7.7 NON-ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM LIMITING CONDITION FOR OPERATION j
3.7.7* Three independent non-accessible area exhaust filter plenums (50% capacity each) shall be OPERABLE with two plenums aligned for operation and one plenum in standby.
APPLICABILITY: MODES 1,2,3, and 4.
ACTION:
With one non-accessible area exhaust filter plenum inoperable, r'estore the inoperable plenum to OPERABLE status within 7 days 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 />. During testing of any inoperable plenum,it is acceptable to place one of the two OPERABLE plenums in standby.
SURVEILLANCE PEQUIREMENTS b
4.7.7 Each non-accessible area exhaust filter plenum shall be demonstrated OPERABLE:
a.
At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that operation occurs for at least 15 minutes; b.
At least once per 18 months, or (1) aftor any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating wlth the exhaust filter plenum by:
1)
Verifying that the exhaust filter plenum satisfies the in-place penetration and bypass leakage testing acceptance criteria of less than 1% when using the test procedure guidance in Regulatory Positions C.S.a, C.S.c and C.5.d of Regulatory Guide 1.52, Revision 2, March 1978, and the flow rate is 66,900 cfm 110% for the train and 22,300 cfm t10% per bank; 2)
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample from each bank of adsorbers of the train obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for methyl lodide penetration of less than 1% when tested at the temperature of 30*C and a relative humidity of 70%;
- Not applicable prior to December 1,1987.
BRAIDWOOD - UNITS 1 & 2 3/4 7-17 AMENDMENT NO. 97; 97
.. +
PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 3)
Verifying a system flow rate of 66,900 cfm i 10% through the train and 22,300 cfm 110% per bank through the exhaust filter t
plenum during operation when tested in accordance with ANSI N510-1980; and 4)
Verifying that with the system operating at a flow rate of 66,900 l
cfm 110% through the train and 22,300 cfm 110% per bank and exhausting through the HEPA-filte; and charcoal adsorbers, the total bypass l
flow of the system and the damper leakage is less than or equal l
to 1% when the system is tested by admitting cold 00P at the system l
intake and the damper leakage rate is determined by either direct measurements or pressure decay measurements at a test pressure of 2 inches of water and the auxiliary building exhaust fans are operating at their rated flow.
l After every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of charcoal adsorber operation, by verifying.
c.
l within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained from each bank of adsorbers of the t
. train in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing cri-teria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, when the average for a methyl iodide penetration of i
less than 1% when tested at a temperature of 30'C and a relative I
humidity of 70%.
d.
At least once per 18 months by:
1)
Verifying for each filter bank of the train that the pressure j
drop across the combined HEPA filters and charcoal adsorber banks of less than 6.0 inches Water Gauge while operating the exhaust filter plenum at a flow rate of 66,900 cfm + 10% through the train and 22,300 cfm 110% per bank; 2)
Verifying that the exhaust filter plenum starts on mar <ual initiation or Safety Injection test signal; and l
3)
Verifying that the system maintains the ECCS equipment rooms at a negative pressure of greater than or equal to 1/4 in. Water Gauge relative to the outside atmosphere during system operation while operating at a flow rate of 66,900 cfm 110% through the train and 22,300 cfm 110% per bank.
e.
After each complete or partial replacement of a HEPA filter bank, by verifying that the exhaust filter plenum satisfies the in place penetration testing acceptance criteria of less than 1% in accord-ance with ANSI N510-1980 for a DOP test aerosol while operating at a flow rate of 66,900 cfm + 10% through the train and 22,300 cfm *10%
i per bank; and 4
i BRAIDWOOD - UNITS 1 & 2 3/4 7-18 AMENDMENT NO. 97; 97
s
- PLANT SYSTEMS BASES 3/4.7.6 CONTROL ROOM VENTILATION SYSTEM The OPERABILITY of the Control Room Ventilation System ensures that: (1) the ambient air temperature does not exceed the allowable temperature for continuous duty rating for the equipment and instrumentation cooled by this system, and (2) the control room will
. remain habitable for operations personnel during and following all credible accident conditions.
Operation of the system with the heaters operating for at least 10 continuous hours in a 31-day period is sufficient to reduce the buildup of moisture on the adsorbers and HEPA filters. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design i
Criterion 19 of Appendix A,10 CFR Part 50. ANSI N510-1980 will be used as a procedural guide for surveillance testing.
1 The surveillance requirement to verify that each control room ventilation system has the capability to remove the required heat load, as determined by the original heat capacity verification test, consists of a combination of testing and calculations. The 18-month frequency is appropriate since significant degradation of the control room ventilation system is slow and not expected over this time period.
i 3/4.7.7 NON ACCESSIBLE AREA EXHAUST FILTER PLENUM VENTILATION SYSTEM The OPERABILITY of the Non-Accessible Area Exhaust Filter Plenum Ventilation System ensures that radioactive materials leaking from the ECCS equipment within the pump rooms following a LOCA are filtered prior to reaching the environment. The operation of this system and the resultant effect on offsite dosage calculations was assumed in the safety analyses. ANSI N510-1980 will be used as a procedural guide for suiveillance testing.
l The Non-Accessible Area Exhaust Filter Plenum Ventilation System is designed such that two plenums are on line and one alenum is in standby. A plenum is in standby if its inlet l
damper is operable but closed, and al remaining components are operable. This alignment ensures proper air flow and prevents fan stall and possible fan damage. The action statement provisions for standby plenums are necessary to accommodate required post maintenance and surveillance testing activities. These provisions allow an operable plenum to be placed in standby while performing testing on an inoperable plenum. The standby plenum will still be capable of being realigned and filtering ECCS cubicle air in the event of a LOCA.
l 3/4.7.8 SNUBBERS l
All snubbers are required OPERABLE to ensure that the structural integrity of the Reactor Coolant System and all other safety-related systems is maintained dunng and following a seismic or other event initiating dynamic loads.
Snubbers are classified and grouped by design and manufacturer but not by size. For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Compan "A" are of the same type. The same design mechanical snubbers manufactured b Company "B" for the purposes of this specification would be of a different type, as would ydraulic snubbers from either manufacturer.
A list of Individual snubbers with detailed information of snubber location and size and of l
systems affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50. The accessibility of each snubber shall be determined and approved by the Onsite Review and Investigative Function. The determination shall be based upon the existing i
radiation levels and the expected time to perform a visual inspection in each snubber location BRAIDWOOD - UNITS 1 & 2 B 3/4 7-4 AMENDMENT NO. 97; 97
. _.